ML20206P598
| ML20206P598 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/31/1987 |
| From: | Eenigenburg E, Maxwell D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 87-215, NUDOCS 8704210229 | |
| Download: ML20206P598 (17) | |
Text
_ _ _ _.
o OPERATING DATA REPORT DOCKET NO. 050-237 DATE April 1. 1987 COMPLETED BY D. C. Maxwell TELEPHONE 815/N2-2920 OPERATING STATUS NOTES 1.
Unit Name:
Dresden II 2.
Reporting Period: March. 1987 3
Licensed Thermal Power (MWt):
2 527 4.
Nameplate Rating (Gross MWe):
828 5.
Design Electrical Rating (Net MWe):
7N 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 I
9 Power Level to Which Restricted, if Any (Net NWe): N/A 10.
Reasons For Restrictions, if Any:
N/A l
This Month Yr-to-Date Cumulative 11.
Hours In Reporting Period 744 2,160 149.400 12.
Number of Hours Reactor Was Critical o
o 119 H01.6 13 Reactor Reserve Shutdown Hours u
o o
14.
Hours Generator On-Line o
o 10s.147.9 l
15.
Unit R9 serve Shutdown Hours 0
0 o
l 16.
Gross Thermal Energy Generated (MWH) o o
216.H77.oH7 l
17 Gross Electrical Energy Generated (MWH) o o
69.402.665 18.
Net Electrical Energy Generated (MWH)
-4,625
-12.512 65.s77.141 19.
Unit Service Factor o
o 10.H 20.
Unit Availability Factor o
o 70.H 21.
Unit Capacity Factor (Using MOC Net) o o
$6.9 22.
Unit Capacity Factor (Using DER Net) o u
55.'l 23 Unit Forced Outage Rate o
o 12.I 24.
Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
N/A i
25.
If Shut Down At End Of Report Period. Estimated Date of Startupi Mitt-April, 19H7 l
0704210P29 070331
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.Mm h PDH ADOCK 00000237 y
H PDH
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OPERATING DATA REPORT DOCKET NO. 050-249 DATE April 1, 1987 COMPLETED BY D. C. Ma.well TELEPHONE 815/042-2920 OPERATING STATUS NOTES 1.
Unit Name: Dresden III 2.
Reporting Period:
March, 1987 3
Licensed Thermal Power (MWt):
2 527 4.
Nameplate Rating (Grcss HWe):
R29 5.
Design Electrical Rating (Net NWe): 791 6.
Maximum Dependable Capacity (Gross MWe): a19 7.
Maximum Dependable capacity (Net NWe):
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 Cumulative 11.
Hours in Reporting Perlod 744 2,160 137,569 12.
Number of Hours Reactor Was Critical 425.8 1.777.6 101,131.2 13 Reactor Reserve Shutdown Hours o
o o
14.
Hours Generator On-Line 116. 6 1.64H.9 9 $,H99. 3 15.
Unit Reserve Shutdown Hours o
o o
16.
Gross Thermal Energy Generated (MWH) 674.406 1.936,119 190,747,816 17.
Gross Electrical Energy Generated (MWH) 215,4Ho 1, 2 69, H'lH 61,692,477 18.
Net Electrical Energy Generated.(MWH) 203.773 1.214,644 58,196,963 19 Unit Service Factor 42.5 76.1 68.1 20.
Unit Availability Factor 42.5 76.'l 68.1 21.
Unit Capacity Factor (Using MDC Net) 15.4 72.7 54.9 22.
Unit Capacity Factor (Using DER Net)
~l4. 5 70.H 53.5 23 Unit Forced Outage Rate 54.5 21.9 12./
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A 25.
If Shut Down At End Of Report Period, Estimated Date of Startup N/A
COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF MARCH, 1987 s
HOUR MAXIMUM DAILY LOAD DAY-ENDING KW 1
0000 0
2 0000 0
3 0000 0
4 0000 0
5 0000 0
6 0000
- 0 7
7 0000 0
8 0000 0
9 0000 0
10 0000 0
11 0000 0
12 0000 0
13 0000 0
14 0000 0
15 0000 0
16 0000 0
17 2100 328.9 18 2300 548.4 19 2400 660.1 20 2200 810.5 21 0400 810.0 22 0000 0
23 2400 565.0 24 2300 769.3 25 1800 807.3 26 1000
'807.5 27 2000 807.7 28 2100 807.9 29 1600 806.6 30 1200 807.9 31 1600 806.2 1
DOCKET NO. 050-237 UNIT NAME II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE April 1, 1987 COMPLETED BY D. C. Maxwell -
TELEPHONE (815) 942-2920 j
REPORT MONTH MARCH. 1987 s.
PETHOD OF LICENSEE CAUSE & CORRECTIVE i
NO.
DATE' TYPEI DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO 1
(HOURS)
DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE.
1 I
9 11-29 S
744:00 C
2 Turbine off-line manually to 10th refueling outage, planned j
Rx scram when mode switch moited from "Run" to " Shutdown'?.
j 1
i i
i 1
1 4
i j
1 2
3 4
F: Forced Reason:
s 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)
(NUREC-0161) l E-Operator, Training & License Examination i
F-Administrative i
G-Operational Error l
I B-Other (Explain)
DOCKET NO. 50-249 UNIT NAME III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE April 1,.1987 COMPLETED BY D. C. Maxwell -
i TELEPHONE (815) 942-2920 l
REPORT MONTH MARCH, 1987 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 2
87-02-26 387:18 A
1 125 VDC Battery Test and HPCI j
(387.3) auxiliary oil pump failure.
3 87-03-21 40:08 G
3 87-006-0 Station Construction personnel (40.1) bumped the Generator Lockout Relay cabinet in the Auxiliary Electric room while pulling cables in area, causing auto
],
turbine trip and subsequent J.
Rx scram.
4 M
I 2
3 4-F: Forced Reason:
s Method:
Exhibit G-Instructione for 8: Scheduled A-Equipuent Failure (Explain) 1-Manual Preparation of Da!.a 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).
(N'!R':G-0161)
E-Operator Training & License Examination.
F-Administrative i
G-Operaticaal Error'
{
[
(i H-Other (Explain) 4 u
.~
AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-237 UNIT II DATE April 1, 1987 COMPLETED BY D. C. Maxwell 4
TELEPHONE 815/942-2920 HONTH March, 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
5 0
21 0
i 6
0 22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
!3 0
29 0
14-0 30 0
0 15 0
31 x
1, 16 0
l 1
l..
l1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-249 UNIT III DATE April 1,1987 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH March, 1987
(
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i I
O 17 212 2
0 18 328 3
0 19 567 4
0 20 718 5
0 21 361 6
0 22 0
7 0
23 251 8
_ i__
24 663 9
0 25 748 10 0
26 779 11 0
27 773 12 0
28 777 13 0
29 766 14 0
30 784 15 0
31 722 16 0
i
~
ORESDEN UNIT 2 k N'y SAFETV RELAIFO HAISTENiNCE NATURE OF LER OR Outt.GE MALFUNCTION N
EQUIPMENT MAINTENANCE NUMoER CAUSE RESULT CORRECTIVE ACTION f W *^* g%-
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'l'k FIC 2-2340-1 CORRECTIVE N/A CHANGED METER AND SETPOINT SCALE, 14 HPCI FLOW CONTROLLER RESPONSE WR 048412 PERFORMED PROCEDURE, LEFT OK q.}-(
METE 2 3
g j
- n.c,
s, CHECKED ALL TRANSMITTERS AND MADE COSEM003 1153 TRANSMITTERS PREVENTIVE N/A
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j.;' c SPAN AND ZERO EFFECT WR 050634 APPROPRIATE SETPOINT CHANGES PER PROCEDURES
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RELAYS C ALIBRATED PER PROCEDURES
(*ISC. U-2 RELAYS PREVENTIVE N/A
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a BUS 24-1 PREVENTIVE N/A RELAYS CALIBRATED PER PROCEDURES WR 058335 O
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r BUS 23-1 PREVENT!VL N/A CALIBRATED RELAYS PER PROCEDURES I'
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O I?'O' WR 058337
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INST ALLED AND REMOVED JUMPER S FOR COO CLOCK CIRCUITRY PREVENTIVE N/A WR U60230 MAINTENANCE g
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S 042-12!!-0022-F 15 PREVENTIVE N/A FUEL INSPECTION COMPLETED PER PROCEDJRE Gaf. FUEL ASSEMBLIES WR 060461
'I F IC 2-23 VJ-1 CORRECTIVE N/A
==
REPL ACED INDICATOR, PERFORMED PROCEDURE O
HPCI FLOW INDICATOR WR D60734 E
a OPT 2352 & DPT 2353 C ORRECTIVE N/A REPLACED 0-RING AND TORQUED COVER HPCI STEiM LINE FLOW WR D60785 O
T2AstSIITTER 0
LT. 2ft3-73A AND 738 CORRECTIVE N/A
- -=
APPLIED THREAD SEALANT AND TORQUE 0 CEICTOR VESSEL LEVEL WR D60787 CONDutT FITTINGS T2ANSMITTERS 2/3 CORE HEIGHT O
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DRESDEN UNIT 2 SAFETY RELATED MAINTEN ANCE b
NATUIE C7 LER OR OUTACE MILFUNCTION EDUIPMENT MalNTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION O
REPLACED COVERS O-RING AND TORQUED FT7541 "5AEB C OR RE CT IV E N/A S8GT SYSTEM FLOW TRANSMITTER WR D60804 COVER 4
PERFORMED PROCEDURE, VERIFIED FLOW LT 2-1351 C ORR EC T IV E N/A U
N ISOLOTION CONDENSER WR D6DS92 THROUGH SENSING LINES w
[
REPLACED TEMPERATURE SWITCH, CALIBRATED p
TS-2-2il-16A CORRECTIVE N/A RE*CTOR AREA. TEMPERATURE SWITCH WR D60899 PER PROCEDURE g
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REPL ACED TEMPER ATURE SWITCH, CALIBRATED TS 2-2',1-160 CORRECTIVE N/A CEACTOR AREA TEMPERATURE SWITCH WR D60902 PER PROCEDURE
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10 2
.A, a
,Wg RE2-7 0H CORRECTIVE N/A REPLACED DRY TUBE PER PROCEDURE v.
U
'.,+;.5 R I;;D 318 DRY TUBE WR D61032 J:
r i.
%-ip 6
% l:
2-17*5-2A THRU D PREVENTIVE N/A
--- =-
CHECKED CALIBRATION PER PROCEDURE
$k (
y ESL LOG RAD MONETORS WR D61181 g
'f b;. A p Mt2,;-
N ADJUSTED BRAKE FOR PROPER TENSION CEFUEL GRAPPLE PREVENTIVE N/A Q."..
MS'1 WR C61440
, 44 q
g p+y t
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PERFORMED WORK PER PROCEDURE CE2-T51A PREVENTIVE N/A
=-- - - - -
O E -
,4 SR7 321 DETECTOR-REPLACEMENT WR D61491 a
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CE2-7518 PREVENT!Vti N/A PERFORMED WORh, PER PROCEDURE
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SRM323 DETECTOR-REPLACEMENT WR D61493 g
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ci CE2-75tG PREVENTIVE N/A PERFORMED WORK PER PROCEDURE oc
'C SR3 C2) DETECTOR-REPLACEMENT WR 061494 M:
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DRESDEN UNIT 2 SAFETY RELATE'O MAINIENANCE O
1 NATURE OF LER O2 OUTAGE MILFUNCTION EQUIPMENT MAINTENINCE NUMBER CAUSE RESULT CORRECTIVE ACTION PERFORMED WORK PER PROCEDURE CE2-760C PREVENTIVE N/A IRM Cl2 DETECTOR-REPLACEMENT WR D61496 Q
COMPLETED WORK PER PROCEDURE RE2-760E PREVENTIVE N/A
=
g 11M 313 DETECTOR-REPLACEMENT WR D61497 s
J l'
COMPLETED WORK PER PROCEDURE RE2-71CD PREVENTIVE N/A IRM Sit DE TECTOR-REPL ACEMENT WR D61500 O
2-2351-G10 CURRFCTIVE N/A INSTALLED NEW TRIP UNIT. P E RF OR M ED ANELDG T:!P SYSTEM WR D61918 PROC EDUR E 4
Nw 1,
REPLACED DAMAGED TRIP UNIT AND PERFORMED C*
2-2331-05 CORRECTIVE N/A O
f.N^ LOG TRIP SYSTEM WR 061919 PR OC EDURE
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ORESDEN UNIT 3 SAFETV RELATED MAINTENANCE J
NATURE OF LER OR DU T s.GE M*.LFUNCTION EQUIPMENT MAINTENANCE NUMdER CAUSE RESULT COR ECTIVE ACTION J
1PZP S CO A & 08-41-C CORRECTIVE N/A RECONNECTE D CABLES PROPERLY FOR LPRM WR 057571 DETECTORS PER PROCEDURES J
ADJUSTED HANGER PER PROCEDURE Call AI Lt-SPRING CAN HANGER PREVENTIVE N/A J_
M-11?30-TOOT WR D57941 J
OW AN) TORUS H2 SENSORS PREVENTIVE N/A PERFORMED PROCEDURL TO CHECK MONITORS WR D59915 ACB CALIBRATION, LLFT OK J
1-lM1-208 CORRECTIVE N/A TRIMMEO OFF 8AD END OF SEALTITE AND J
30RUS TO CE AC TOR eLOG VACUUM WR D60740 RECONNECTED 4i BREAKE2 1.t CORRECTED SP! KING PROBLFM WHILE LP!.M 30-32-33 CORRFCTIVE N/A O
WR 060810 P ERF OR MING PROCEDURE, LEFT OK se n
- g 3-1C3D-10060 CORRECTIVE N/A REROUTED SEALTITC AND PERFORMED
/ >
/
CORE SPIAY PUMP DISCHARGE WR D60908 PROC E DUR E O
HELDE3 PIESSURE SWITCH FOR AUTO
^'3/
ELOWOOWN PERMISSIVE REACTOR CLDG INTERLOCK 000RS PREVENTIVE N/A CHANGED MAGNETIC SWITCH AND 000R MAGNET, WR D61087 LEFT OK
'J L T 3-li26 CORRECTIVE N/A RECALIBRATED WITH THE DRY METHOD AND N
TORUS N AIROW RANGE TR ANSMITTER WR D61120 PERFORMED PROCEDURE, LtFT OK O
LP:M 3C CS-33 (APRM 228 CORRECTIVE N/A CORRLCTED SPIKING PROBLEM WHILE WR D61235 PERFORMING PROCEDURE, LEFT OK g
y.Y, LP;M 3C 08-33 C OR REC T IVE N/A PERF ORMED PROCEDURE, ND PROBLEMS FOUND WR 061236 r-9 b
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ORE 5 DEN UNIT 3 SAFETV RELATED MAINI'ENANCE ttATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NU* DER CAUSE RESULT CORRECTIVE ACTION REPLACEO RELAY AND TESTF0 PER 3-T50-100 CORAECTIVE N/A
'APiM 6 WR 061569 PROCEDURE, LEFT OK RESE T PRESSURE REGULATOR TO CLEAR ALARM, 3-2404 CORREECTIVE N/A H2 02 MONITOR SYSTEM A WR 061931 LEFT OK
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EQulPMENT M*INTENANCE NUMdER CAUSE RESULT CORRECTIVE t.CTION
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. UNIQUE-REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS
. Relief valve operations'during the reporting period March, 1987 are-
- summarized.in the following table.- The table includes information as to-which relief valve was actuated, howit was_ actuated, and the circum-stances resulting in its actuation..
Valves Description Unit' Reporting Period Actuated Actuations ~-Conditions of Events
~2 03-01-87 to 03-31-87 None 3
03-01-87 to 03-31-87 None p
- - - = -
~
s
SUMMARY
OF OPERATING-EXPERIENCE UNIT TWO MARCH, 1987,
'03-01-87 to 03-31-87 ~
Unit 2's refueling outage continued throughout the month. Major' work included:
- Primary containment - local leak rate tests
- Primary containment - integrated leak rate test
- Reactor vessel'ASME hydrostatic pressure test
- Normal pump (s) and valve (s) maintenance 4
6 6
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SUMMARY
0F OPERATING EXPERIENCE UNIT'THREE 1
MARCHi 1987 03-01-87 to 03-17 Unit 3 entered the month off-line for repair ofiche; auxiliary oil pump for HPCI-and replacement of certain
. torus area snubbers was accomplished. While preparing
.to bring the unit on-line, the #4 turbine control-
~
A valve malfunctioned an'd a piece of metal was removed from the stem area of the valve upon' investigation.
Also, there was an EHC oil leak that was repaired.
{;
The reactor was made. critical March 13, at 0239 hours0.00277 days <br />0.0664 hours <br />3.95172e-4 weeks <br />9.09395e-5 months <br />.
l and the turbine was brought.on-line at.0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> of.
i March 17.
I 03-18-87 to 03-21-87 When the unit reached 30% power, half-core scram test-3 ing was performed and when completed.. load'was increased-1 i
steadily until 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> of March 21,-when a turbine trip and subsequent reactor scram occurred. This automatic trip and scram was caused by Station Constru-tion personnel that pumped the Generator' Lockout Relay cabinet in the Auxiliary'Electsic room while pulling 4
cables in the area.-
f s
~
03-22-87 to 03-31-87 After determinations of causes and corrective action were completed, the reactor was made critical on.
]~
March 22, at 1459 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.551495e-4 months <br />'and the-turbine was brought.
on-line at 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br /> of March 23.
The unit steadily increased load.to maximum core flow and operated the remainder of the' month with-a capacity factor of 34.81% and an availability of 42.55%..
4 5
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=
Commonwealth Edison Dresden Nulle:r Power St; tion R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 April 1, 1987 EDE LTR:
87-215 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 March, 1987. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.
Sincerely, E. D. Eenig nb g Station Mana 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 Nuclear Licensing Administrator 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.
Comptro11er's Office PIP Coordinator INPO Records Center File /NRC Op. Data File / Numerical 3