ML20197H633

Monthly Operating Repts for Apr 1986

ML20197H633
Person / Time
Site:	Dresden
Issue date:	04/30/1986
From:	Maxwell D, Scott D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-327, NUDOCS 8605190222
Download: ML20197H633 (19)

Text

.

OPERATING DATA REPORT DOCKET NO. 050-237 DATE May 1, 1986 COMPLETED BY D. C. M m ell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name:

Dresden II 2.

Reporting Period:

April, 1986 i

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 (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 II.

Hours in Reporting Period 719 2.879 139.943 12.

Number of Hours Reactor Was Critical 637.3 2.704.4 106.402.0 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 579.5 2.446.6 101.431.2 15 Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.344.204 5.699.529 207.333.168 17 Gross Electrical Energy Generated (MWH) 437.095 1.858.070 66.357.833

18. Net Electrical Energy Generated.(MWH) 416.825 1.772.074 62.708.188 19 Unit Service Factor 80.6 85.0 72.5 20.

Unit Availability Factor 80.6 85.0 72.5 21.

Unit Capacity Factor (Using MDC Net) 75.1 79.7 58.0 22.

Unit Capacity Factor (Using DER Net) 73.0 77.5 56.4 23 Unit Forced Outage Rate 19.4 15.0 12.4 24.

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

Mid-May for a weekend snubber inspection.

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

N/A 8605190222 860430 PDR ADOCK 05000237 R

PER

/I

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

Unit Name: Dresden III 2.

Reporting Period:

April, 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 This Month Yr-to-Date Cumu.l.a t ive.

11.

Hours in Reporting Period 719 2,879 129,528 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 89,793.3 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)

-4,728

-19.433 55.706,851 15 Unit Service Factor 0

0 69.3 20.

Unit Availability Factor 0

0 69.3 21.

Unit Capacity Factor (Using MDC Net) 0 0

55.6 22.

Unit Capacity Factor (Using DER Net) 0 0

54.2 23.

Unit Forced Outage Rate 0

0 12.4 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duraticn 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. 050-137 UNIT II DATE May 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH April, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 699 17 770 2

8 18 780 3

0 19 690 4

0 20 770 5

0 21 792 6

0 22 761 7

0 23 793 8

525 24 779

~

9 633 25 744 10 648 26 715 11 765 27 685 12 740 28 704 13 654 29 737 14 764 30 749 15 760 31 16 771

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-249 UNIT III DATE May 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH April, 1986 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

5 0

21 0

6

.0 22 0

7 0

23 0

8 0

24 0

0 9

25 0

0 10 26 0

ii 27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 16 0

COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD 1

MONTH OF APRIL, 1986 i

HOUR MAXIMUM DAILY LOAD DAY ENDING KW i

I 1800 812,600 i

2 0100 201,500 3

0000 0

4 0000 0

5 0000 0

6 0000 0

7 2400 133,000 8

2300 684,500 9

1700 782,800 j

10 2400 761,300 11 1500 815,900 12 0100 794,900 13 2400 737,900 14 1700 813,700 15 0100 801,800 16 1300 815,900 i

17 0100 809,500 18 0400 805,500 19 0300 799,200 20 1400 813,400 l

J21 1800 814,300 22 1300 823,400 23 1300 823,200 24 1500 821,700 25 0100 820,000 26 2200 769,600 27 1100 772,700 28 1500 759,900 29 1900 815,500 30 0100 811,700

DOCKET NO. 050-237 UNIT NAME II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE May 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT MONTH APRIL, 1986 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 j

4 86-04-02 F

139:32 H

1 86-006-0 Manually shut down to install (139.5) seismic restraints (bolting) on control room panels.

t 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-Administrr.tive i

G-Operational Error H-Other (Explain) i

l DOCKET NO. 050-249 UNIT NAME III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE May 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT MONTH APRIL, 1986 HETHOD 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

85-10-23 S

719:00 C

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

1 1

2 3

4 F

Forced Reason:

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 G-Operational Error

{

H-Other (Explain) e

pRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-203-1D MSIV Corrective W.R'.

1. 48709 N/A Adjusted limit switch arm..

Limit Switch l

AH 502-2402-A Preventive W.R. #48706' N/A Investigated and adjusted Cam H2 sensor.

Drywall and Torus Cam H2 Sznsor i

Accuxulator Corrective W.R. #50943 N/A Leaking valve - replaced packing.

06-31.

Accumulator Corrective W.R. #50650 N/A Could not totally repack valve - did add 26-27's 127 3 rings of packing.

(Scram) Valve Preven'ive W.R. #51024 N/A Performed SP-86-2-25 to calibrate AH0 Monitor t

2 2 monitor with manufacturer representa-tive's assistance.

2A-1102

' Corrective W.R. #51077 N/A Adjusted packing for leaking pump.

2%'Rx Bldg.

Preventive W.R. #51271

.N/A Removed temporarily and reinstalled.

[

Exhaust Fan-Hradar Sway I

Brace 2-1705-6A.

Corrective W.R. #51284 N/A Replaced sensor - calibrated equipment with temporary procedure.

2-503-B "B" Preventive W.R. #41484-N/A Checked switch calibration - works fine.-

Condsnsor Low Vacuum Switch I

PS.2-261-30P Corrective W.R. #51698 N/A Replaced pressure switch and checked switch calibration.

1459-B Core Preventive W.R. #50392 N/A Checked transmitter - no problem found.

l Spray Header Dpt, Performed DIS 1400-1 Rev. 3 on dpt.

1459-B.

DRESDEN UNIT 2

~

SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION' EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT-CORRECTIVE ACTION TS-1-5 (J-U) Rx Corrective W.R.

1. 51160 N/A Adjusted setpoint to 150*F, verified Water Cleanup alarm locally / control room per DAP 11-11,

. Area Temporary Rev. 6.

Alarm Channel "A" MSL Corrective W.R. #53018 N/A Removed failed rad monitor. Replaced Rad Monitor monitor and calibrated.

2-220-102 Corrective W.R. #53103 N/A Replaced valve with four rings of 1625-R2 circulation packing. Back seated valve, per instruc-Loop Sample tions on work request.

Isolation Valve e

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION FT-3-1549B Preventive W.R.

1. 42223 N/A Inspected and repaired calibrated transmitter.

FT-3-1549A Preventive W.R. #42224 N/A Inspected and repaired calibrated transmitter.

FT-3-1542B LPCI Preventive W.R. #42225 N/A Inspected and repaired calibrated Flow Transmitter transmitter.

PT-3-1460A Core Preventive W.R.

1. 42235 N/A Inspected and repaired calibrated Spray Pressure transmitter.

Transmitter R~ actor Low Low Preventive W.R.

1. 43501 N/A Changed alarm card and manually actuated Lt; val B Alarm relays to reset - tested ok.

3-1502C 3C LPCI Preventive W.R.

1. 48861 N/A Drilled k" weep hole in main junction Pump box of motor.

Inspected for environ-mental qualification.

3-1401-A 3A Core Preventive W.R. #50648 N/A Replaced sealtite to motor heater junc-Spray Pump tion box.

1510-M-303 Corrective W.R. #50949 N/A Adjusted spring can tension to 1800 lbs (3-1510-H55) 30 per work instructions.

CCSW Pump Dis-charg: Line Support 3-2540-15B ACAD-Corrective W.R. #50989 N/A Replaced capacitor Cl on main circuit CAM Inlet Flow board. Replaced op amp IC1 and C205 Control 4-20MA card.

250 VDC Battery Preventive W.R. #51158 N/A Charged cell #101 for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> check

1. 101 voltage; specific gravity.

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION DTS-31 Leak Rate Preventive W.R.

1. 51514 N/A Calibrated DTS-31 via DIP 010-4, Rev. 2 Tcst Box utilizing DIP 2100-8 Rev. 2.

DTS-32 Leak Rate Preventive W.R. #51515 N/A Calibrated DTS-32 via DK-23-DIP 010-4, T:st Box Rev. 2.

3-1502-B 3B LPCI Preventive W.R. #48862 N/A Drilled \\" week hole in main junction Pump box of motor.

Inspected for environ-mental qualification.

3-1502-A 3A LPCI Preventive W.R.

1. 48863 N/A Drilled h" week hole in main junction Pump box of motor.

Inspected for environ-mental qualification.

3-1502-D 3D LPCI Preventive W.R.

1. 48866 N/A Drilled k" week hole in main junction Pump box of motor.

Inspected for environ-mental qualification.

3-705-002 LPRM Corrective W.R. #47864 N/A Work will be performed by W.R. #45749.48-49C FT-3-1542A LPCI Preventive W.R. #42226 N/A Performed DIS 1500-11 on check sheets Flow Transmitter 1 and 2.

Br.nch Check Preventive W.R.

1. 48963 N/A Removed bench checked valve and rein-3-263-2-19A Flow stalled on instrument rack 2203-5.

ch::ck Valve 3-263-2-17A Preventive W.R. #48964 N/A Removed, tested and installed instrument Instrument Rack rack 2203-5, 2253-75A and C flow check Flow Check valves.

3-263-2-15A Preventive W.R. #48965 N/A Removed, tested and installed instrument Instrument Rack rack 2203-5, 2253-75A and C flow check Flow Check valves.

-__m

__m

-.m DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE-ACTION 3-263-2-15A Preventive W.R. #48966 N/A Removed, tested and installed instrument.

InstrumentRack rack 2203-5, 2253-75A and C flow check.

i Flow Check valves.

4 3-263-2-11 Wide Preventive W.R. #48967 N/A Removed, tested and installed wide range

~

Range Level Flow level flow check valve.

Chnck i.3-262-6B Recirc.

Preventive W.R. #48968 N/A Removed, tested and installed wide range Pump Seal Flow level flow cieck valve.

l l

Check Valve.

l 3-262-2-6A Preventive W.R. #48969 N/A Removed, tested and installed wide range-E

'Recirc.~ Pump level flow check. valve.

Seal Flow Check 3-262-5B Recirc.

Preventive W.R. #48970 N/A Removed, tested and installed wide range Pump Seal Flow level flow check valve.

Check 3-262-5A Recire.

~ Preventive W.R. #48971 N/A

. Removed, tested and installed wide range Pump Seal Flow level flow check valve.

Chsek' 3-220-54 Flange Preventive W.R. #48972 N/A Bench' checked flange seal leak-off flow Ssal Leak-Off check valve.

Flow Check U-3 Scram Dis-Preventive W.R. #49465 N/A.

Removed sway strut, reinstalled pins, charge Header washers and tied off bar on end.

Rein-Sway Strut stalled sway strut.

LT-3-263-61 Rx Preventive W.R. #51056

' N/A Performed check sheets 1 and 2 via MMP

' L: val-Transmitter 51056.

Calibrated transmitter and indicators.

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - APRIL, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION

1. 3 Diesel Preventive W.R.

1. 51129 N/A Performed 3 month inspection per DMP G:ntrator 600-2, Rev.

1.

3-1705-3B "B" Corrective W.R.

1. 51554 N/A Replaced amplifier tubes valve 1 and 2, Off-Gas Rad.

performed calibration via applicable Monitor sec. DCP 2700-11, Rev. 3.

PT-3-1625 Preventive W.R.

1. 42216 N/A Performed check sheets 1 and 2 via MMP Pressure Sup-42216.

Performed DIS 1600-10, Rev. 6 for pr:ssion Pres-DTS 1625.

sure Trans.

FT-3-1461B Core Preventive W.R.

1. 42236 N/A Performed check lists.

Installed new Spray Flow Trans cover on transmitter.

FT-3-1461A Core Preventive W.R.

1. 42237 N/A Performed check lists.

Installed new Spray Flow Trans cover on transmitter.

R actor Vessel Praventive W.R.

1. 46131 N/A Assembled system and installed Rx head Ventilation flanges (north, south), removed vent system.

3:1101-5 SBLC Corrective W.R.

1. 50913 N/A Removed packing, cleaned, repacked and Suction Header replaced valve.

Drain Valve

-.m..._

__.m DRESDEN UNIT 2/3 E

SAFETY RELATED MAINTENANCE - APRIL, 1986 j

l l.

LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION LPRM Amplifier Corrective W.R. #49853 N/A LPRM amplifier card caused 0833C at.4.-

Card-Replaced Q-12 trans. dr.

Bench checked l

ok.

" Quad Trip' Card Corrective W.R. #49854 N/A Card broken, R3-15m kw, 5% replace resister R-3, performed bench che'ck.

2/3 Diesel Preventive W.R.

1. 50322 N/A Performed annual inspection per work Gnnerator instructions.

2/3 Diesel Preventive W.R. #50324 N/A Performed annual inspection per work LGenerator instructions.

SBGT X-Tie Corrective W.R. #50620 N/A Replaced broken limit swiEch.

Insured Dr: aper Closed proper operation.

Limit Switch 2(3)-1106A'and Preventive W.R.' #51296 N/A Performed special procedere SP 86-2-27 to assure continuity of internal circuits.3 B SBLC' Squib-Valva Trigger W

A:srmbly FIC 2/3-7541-28A Corrective W.R. #51388 N/A-Recalibrated setpoint indication'as "A" SBCT System instructed - 400 CFM higher than the Flow Controller

-flow to.be controlled.

q 2/3 6601 2/3 Corrective W.R. #51588 N/A Tightened leaks as tagged. Verified no leakage 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> later.

l Diesel Genera-ter l. Aran Rad Monitor Corrective W.R. #51615 N/A ARM sensor failed no response. Replaced

[

'S nzor Converter GM tube - calibrated according to proce-dure.

F20.VRC.D.S. For Corrective W.R. #51664 N/A.

Replaced Q2 trans. and diode VRI. Verify-APRM/RBM output voltage greater than -20 VDC.'

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i UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period'of April, 1986 are

" summarized in the following table. The table includes information'as to 3

shich. relief valve was actuated, how it was actuated, and the circum-

,. st.tucis resulting in its actuation.

+

t Valves

- Description Unit Reporting Period Actuated Actuations Conditions' of Events 2.

04-01-86 to 04-30-86 None L

3 04-01-86 to 04-30.86., None 9

b f

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. au S

y A,

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SUMMARY

OF OPERATING EXPERIENCE UNIT TWO APRIL, 1986 04-01-86 to 04-07-86 Unit 2 entered the month at maximum core flow, and operated until 0313 hours0.00362 days <br />0.0869 hours <br />5.175265e-4 weeks <br />1.190965e-4 months <br /> of April 2, 1986, when it was manually taken off-line per an Administrative decision to install seismic restraints (bolting) on control room panels. The reactor was manually shut-down at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br /> of the same day. After instal-lation of the bolting, the reactor was made critical

.on April 5, 1986 at 1332 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.06826e-4 months <br />. During the startup routines a problem developed on a #3 C.I.V. limit switch, which required repairs, and after the completion, the turbine was brought on-line April 7, 1986 at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />.

04-08-86 to 04-30-86 Load was steadily increased to maximum core flow and operated through the remainder of the month. Availa-bility is 80.59% and capacity factor is 72.88%.

4

SUMMARY

OF OPERATING EXPERIENCE UNIT THREE i

I APRIL, 1986 04-01-86 to 04-30-86 Refueling outage activities continued throughout the entire period. The unit is presently scheduled to startup in mid-June, 1986. Major work includes:

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

- Replacement of the recirculation piping

- ISI inspections

- LLRT I

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O Morris, Illinois 60450 Commonwealth Edison Dresden Nucle:r Power St:.ti:n g

R.R. #1 Telephone 815/942-2920 May 1, 1986 DJS LTR: 86-327 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 April, 1986. This information is supplied to your office per time instructions set forth in Regulatory Guide 1.16.

Sincerely, i

D.

. Scott Station Manager j

Dresden Nuclear Power Statio' DJS:DCM:hjb Enclosure cc:

Region III, Regulatory Operations, U.S. NRC j

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 INP0 Records Center File /NRC Op. Data File / Numerical

' I i

L