ML20093E878

Monthly Operating Repts for June 1984

ML20093E878
Person / Time
Site:	Dresden
Issue date:	06/30/1984
From:	Schroeder B, Scott D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DJS-LTR:-84-669, NUDOCS 8407180158
Download: ML20093E878 (16)

Text

.. __

e

+

OPERATING DATA REPORT DOCKET NO. 050-237 DATE July 5, 1984 COMPLETED BY B. A. Schroeder TELEPHONE (815) 942-2920_

OPERATING STATUS NOTES

1. Unit Name: Dresden II

2. Reporting Period: Jung. 1984 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 NWe): 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 1

4 This Month Yr-to-Date Cumulative.

II. Hours in Reporting Period 720 4367

12. 123.887 Number of Hours Reactor Was Critical sss.4 4202.4 96.426.9

13. Reactor Reserve Shutdown Hours 0 0 0 4

14. Hours Generator On-Line aos.3 4120.5 95.026.5 15 Unit Rese,rve Shutdown Hours o 0 0 j 16. Gross Thermal Energy Generated (MWH)

' 1.1R4 s10 o asa toA 186.553.132 17 Gross Electrical Energy Generated (MWH) 378.824 3:206'017. 59.708.216

18. Net Electrical Energy Generated.(MWH) 1ss.303 1.naa_oga sn_a12.348 19 . Unit Service Factor 68.79 94.0 77.0

20. Unit Availability Factor 68.79 94.0

21. 77.0 l

Unit Capacity Factor (Using MDC Net) 63.92 90.0 59.0

22. Unit Capacity Factor (Using DER Net) 62.15 88.0 57.0

23. Unit Forced Outage Rate 31.21 6.0 11.0

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

Sentember 3. 1984 for refueling

25. If Shut Down At. End Of Report Period. Estimated Date of Startup: July 1. 1984 99

OPERATING DATA REPORT DOCKET NO. 050-249 DATE July 5, 1984 COMPLETED BY B. A. Schroeder TELEPHONE im g 947_797n OPERATING STATUS NOTES I. Unit Name: Dresden IIE

2. Reporting Period: June. 1984 3 Licensed Thermal Power (MWt): 2,527

4. Nameplate Rating (Gross NWe): 828 5 Design Electrical Rating (Net MWe): 794

6. Maximum Dependable Capacity (Gross MWe): 812

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 Cumula t i.ve .

11. Hours in Reporting Period 7?n 4.367 111.672

12. Nember of Hours Reactor Was Critical n 126.1 P1.171.1

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 0 0 vo.rAi_i

15. Unit Reserve Shutdown Hours 0 0 o

16. Gross Thermal Energy Generated (MWH) 0 0 159.961.098 17 Gross Electrical Energy Generated (MWH) 0 0 51.952.919

18. Net Electrical Energy Generated.(MWH) -7452 29.853 49.200.73I 19 Unit Service Factor 0 0 70.0

, 20. Unit Availability Factor 0 0 70.0

21. Unit Capacity Factor (Using MDC Net) 0 0 56.0

22. Unit Capacity Factor (Using DER Net) 0 0 55.0 23 Unit Forced Outage Rate 0 o 13.0

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup: Late July, 1984 g, A ,_M -

• 9-*F W _8P. M _? N _ . . .

DOCKET NO. 050-237 UNIT NAME Dr~d =n II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE July 5. 1984 COMPLETED BY B. A. Schroeder TELEP110NE (815) 942-2920 REPORT MONTil June. 1984 .

MET 110D OF LICENSEE NO. DATE TYPEl CAUSE & CORRECTIVE DURATION REASON 2 SIIUTTING EVENT SYSTEM COMPONENT ACTION TO (Il0URS) DOWN REACTOR 3 REPORT # CODE 4 CODES PREVENT RECURRENCE 2 84-6-21 F 224.6 A 3 -- -- --

2A feed regulator (valve) opera-tor stem became separated from the valve stem. Reactor scrammec on low water level. Valve repaired.

s s

1 2 3 4 F: Forced Reason:

S: Scheduled. Method: Exhibit C-Instructions for A-Equipment Failure (Explain) 1-Manual l Preparation of Data B-Maintenance or Test 2-Manual' Scram C-Refueling Entry Sheets for Licensee D-Regulatory Restriction 3-Automatic Scram Event Report ( ) File 4-Other (Explain) MUREG-0161)

E-Operator Training & Licence Examination F-Aoministrative '

G-Operational Error H-Other (Explain) t . . .. .

DOCKET NO 050-249 UNIT NAMEDresden III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE July 5. 1984 COMPLETED BY B. A. Schroeder TELEPHONE (815) 942-2920 REPORT MONTil .1,,,,, _ ioas ,

METHOD OF LICENSEE CAUSE & CORRECTIVE NO. DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS) DOWN REACTOR 3 REPORT # CODE 4 CODES PREVENT RECURRENCE 8 83-9-30 S 720 C 1 Main turbine repair.

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 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)

Ysar AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. oso-2n UtilT II i

DATE July 5, 1984 COMPLETED BY B. A. ' Schroeder TELEPHONE 815/942-2920 MONTH June. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA!LY POWER LEVEL (MWe-Net) (MWe-Net)

I 555 17 708 2 613 18 752 3 725 19 763 4 761 20 762 Q 5 768 21 482 6 767 22 0 7 765 23 o 8 767 24 o 9 691 25 0 10 754 26 o 11 756 27 o 12 763 28 0 13 763 29 o 14 753 30 0 15 775 31

]

16 612 k . . . .

- - - - ~ - - - - - -

f, ,

s

p. .,

AVERAGE DAILY UNIT POWER LEVEL t v 'b '

DOCKET NO. nsn-?t.o UNIT III m

DATE July 5, 1983 COMPLETED BY B. A. Schroeder TELEPHONE 815/942-2920 M0!4TH June. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) t 1 0 17 o 2 o 18 0 3 0 19 0

' ~

4 0 20 0 5 0 21 0 6 0 22 o 7 0 .23 0 _

8 0 24 0 9 0 25 0 10 0 26 0

11 0 27 0

'12 0 28 0 13 0 29 0 -

14 0 30 0 15 0 31 --

16 0 O

DRESDEN UNIT 2 '

4 il SAFETY RELATED MAINTENANCE - JUNE, 1984

[

'I

• NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION i Refuel Preventive W.R. #34665 N/A N/A Adjusted up and down mast speed control. f Grapple  :

I I

M02-1301-2 Preventive W.R. #35382 ---

N/A N/A Replaced overload relay and overload Valve heaters.

' Accumulator Preventive W.R. #34093 ---

N/A N/A Replaced accumulator.

' #06-31 Press Fitting Refuel Preventive W.R. #32765 ---

N/A N/A Installed jumper.

Grapple j i

M02-1201-2 Preventive W.R. #33931 --

N/A N/A Cleaned contact' point inside of socket and Local Con- relamped.

trol Station Light Bulb Accumulator Preventive W.R. #33962 N/A N/A Replaced switch.

-#34-11.

Accumulator Preventive W.R. #34180 N/A N/A Recalibrated alarm to proper set point.

1. 34-39 (J-10)

LPRM Group Preventive W.R. #35105 ---

N/A N/A Replaced switch assembly.

II Accumulator Preventive W.R. #35668 ---

N/A N/A Replaced accumulator and 2 o-rings.

1. 14-43 2A LPCI Heat Preventive W.R. #35616 ---

N/A N/A Adjusted nuts.

Exchanger

_ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ __ _ __ ____b

o DRESDEN UNIT 2 ,

SAFETY RELATED MAINTENANCE - JUNE, 1984 NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Offgts Log Preventive W.R. #31768 N/A N/A Repaired and calibrated spare rad monitor.

Rid Monitor 1705-3A Accumulator- Preventive W.R. #34998 N/A N/A Recalibrated accumulator pressure switch.

1. 34-39, EPN l

1. 2-0305-130 j

[

M01301-2 Preventive W.R. #35475 N/A N/A Investigated MO valve tripping problem. No i abnormality noted.

D/G Cooling Preventive W.R. #34424 ---

N/A N/A Repaired a defective alarm card.

Water PP Alarm  !

2-2301-10 Preventive W.R. #35273 N/A N/A Investigated ground problem. Removed and i' HPCI Test dryed out water found in switch junction Discharge to box. l Cond. Storage M02-1301-2 Preventive W.R. #35317 ---

N/A N/A Investigated MO valve tripping problem.

Tightened loose terminal point and lubed i as needed.

I 6

i f

!l

DRESDEN UNIT 3

• i SAFETY RELATED MAINTENANCE - JUNE, 1984 ,

i NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION D3 MSIV Edlot Preventive W.R. #27919 N/A N/A Rebuilt and tested 3-way and 4-way pilot Velva, EPN valve.

1. 3-203-2B .i LPRM Four Preventive W.R. #33773 N/A N/A Replaced quad trip card in Z28.

Rod Display I U3 IRM #18, Preventive W.R. #34451 ---

N/A N/A Replaced detector.

EPN #RE3-760H ,

t B-Loop Preventive W.R. #33623 N/A N/A Removed and replaced obstructions to allow (Wald 28-15) weld overlay. ,

U3 Rx Recire, ,

Piping Over- ,

Icy l l

Wald #28-6 Preventive W.R. #32796 N/A N/A Removed and replaced 8" I beam to allow f Rx Rtcire, weld overlay. j System Support 3 "A" SBLC Preventive W.R. #33735 ---

N/A N/A Replaced 3 bushings - I set of packing.  ?

Pump, EPN

1. D3-Il02A 3-A R:cire. Preventive W.R. #33756 N/A N/A Removed core samples.

Pipe 28-10 i I

Drywell D3 Preventive W.R. #27890 N/A N/A Incpected personal and equipment hatch.  !

Ptr:onnl/ {

Equip. Door i

t f

-__g .. _- - . ~ -

z.-_.

' .h

,q l'

DRESDEN UNIT 3 .

SAFETY RELATED MAINTENANCE - JUNE, 1984 p'

i NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l; 3-1503-B Preventive W.R. #27849 N/A N/A Removed and replaced heads for cleaning.

LPCI Hmat (

Exchanger l AO-3-220-47 Preventive W.R. #34689 N/A N/A Installed new air diaphgram and air regu-lator.

HPCI Check Preventive W.R. #28337 N/A N/A Removed and replaced top cover from valve.

Velva . 3-230 l-  !

39 [

i D3-1301-10 Preventive W.R. #23288 ---

N/A N/A Repacked valve with grafoil packing.

Valva l t

3-1402-25A Preventive W.R. #33722 ---

N/A N/A Installed limitorque operator.

A0-3-1402-9A Preventive W.R. #31761 N/A N/A Removed drain valves and cap.

rsin Valves Local Control Preventive W.R. #33225 N/A N/A Relamped and cycled valve to' verify proper Hecd Spray light indication.

M03-205-2-4 MO-3-1501- Preventive'W.R. #33676 N/A N/A Replaced auxiliary contacts.

27B RBCCW Return Preventive W.R. #29174 N/A N/A Replaced valve operator, from Drywell M03-3706 Torus to Preventive W.R. #30530 N/A N/A Removed and installed vacuum breaker, i, Drywall  !;

Vacuum  :

Brar.kars l i

___ _ _ - ---- I

p i

DRESDEN UNIT 3

• SAFETY RELATED MAINTENANCE - JUNE, 1984

!l l

NATURE OF LER OR OUTAGE MALFUNCTION 4 EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION ..

Torus to Preventive W.R. #30806 ---

N/A N/A Removed and installed vacuum breakers. i Drywall t, Vccuum j Breckars j I'

D3 600 PSI Preventive W.R. #34077 N/A N/A Investigated full scram problem. Replaced {

BypI0s Scram defective jumper. f.

P53-263-51A [

End B I' I

Drywall High Preventive W.R. #31329 ---

N/A N/A Investigated and repaired defective diodes.

Rad Monitor, EPN #3-2419-A or B LPRM #16-33A Preventive W.R. #34469 N/A N/A Repaired defective connectar.

U3 480V Bus Preventive W.R. #30685 N/A N/A Installed and removed jumpers. I Nos. 35,36, f 37,38 cnd 39 i Cora Spray Preventive W.R. #33227 ---

N/A N/A Replaced defective indicating light.

M03-1402-25C 3-1402-25A Preventive W.R. #33708 ---

N/A N/A Removed valve operator so it can be used on Unit 2.  ;

i i

l I

i i

SUMMARY

OF OPERATING EXPERIENCE UNIT ONE JUNE, 1984 The status of Unit I remains shutdown with all fuel removed. The environ-ment and equipment continues to be maintained as needed.

Chemical cleaning has essentially been unchanged since the last monthly report (December, 1982) about Unit 1. Recently there has been an increase in activity. Presently all systems are undergoing preoperational checks -

plus the training of operators at the controls. A number of preoperational tests still remain and are expected to be completed shortly.

A defective discharge outlet (cracked) on the concentrator recirculation pump may delay the commencement of chemical cleaning (scheduled for late 4 July, 1984). A number of Inservice Inspections have already been performed (Ultrasonic Inspection) to verify the condition of important welds.

SUMMARY

OF OPERATING EXPERIENCE UNIT TWO JUNE, 1984 06-01 to 06-21 Unit 2 entered the month operating at a power level of 808 MWe and operated continuously until the 21st when the 2A feed regulating valve failed causing low reactor water level followed by a reactor scram. The valve operator stem separated from the valve stem causing the valve to go shut.

06-21 to 06-30 Repairs were made to the 2A feed regulating valve. While in the process of starting up, problems developed with the cleanup auxiliary pump (bearing problems). In addition, when an outage war taken on an instrument bus feed breaker to repair some limit switches (2301-65), the reactor opera-tor noted that several chart recorders and valve indications were also de-energized. Initial investigation has indicated that a proposed wiring change in 1969 was never completed.

A special test of five additional circuits were tested and compaired to the wiring / schematic diagram and no similar discrepencies were noted. (Reactor was shutdown until the investigation and tests were completed.)

During this shutdown period, the required 6 month (+ 25%)

snubber inspection was performed on the inaccessible snubbers that were found inoperative during the previous refueling out-age. All inaccessible snubbers were visually inspected and no adverse conditions noted.

The unit remained off-line through the end of the period.

The unit achieved a capacity factor of 63.08% and an availa-bility of 68.8%.

e

SUMMARY

OF OPERATING EXPERIENCE UNIT THREE JUNE, 1984 06-01 to 06-30 Unit 3 remained shutdown and off-line the entire period.

Work on the main turbine (H.P. rotor) continues. The rotor has been placed back in the casing with final assembly in progress.

The unit is expected to return to service sometime late July, 1984.

l i

. l UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actua-tion.

Valves No. & Type Plant Description Unit Date Actuated Actuations Conditions of Events 1 06-01-84 to 06-30-84 None 2 " "

None 3 None i

f i

l 4

- f'O, Commonwealth Edison

'[ C- ) Dresden Nuclear Power St; tion

{ 33; Y- RR.#1 Morris, Illinois 00450

\N TeleWwne 815/M2-2920 l

July 5, 1984 1.

, DJS LTR: 84-669 i.

t Director, Office of Inspection and Enforcement United States Nuclear Regulatory i Commission  ;

Washington, D.C. 20555 i

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 Regulatory Guide 1.16.

Sincerely,

/ a) 5 D. . Scott Station Superintendent Dresden Nuclear Power Station i DJS: BAS:hjb Enclosure I 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 Nuc. Sta. Div..Vice Pres.

Manager, Tech. Serv. Nuc. Sta.

l Tech. Staff EA l l On-Site NRC Inspector Sta. Nuc. Eng. Dept.

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

File / Numerical f?

9 \s .

1 l

l

. _ _ . _ _ _.m _ , - - . . , - _ . . _

--___ _ _ __.,__m . . . . _ _ _ -