ML20199B825
| ML20199B825 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/31/1986 |
| From: | Maxwell D, Scott D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 86-385, NUDOCS 8606170231 | |
| Download: ML20199B825 (16) | |
Text
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, OPERATING DATA REPORT o-DOCKET NO. 050-237 DATE June 2,1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.
Unit Name:
Dresden II 2.
Reporting Period:
May, 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 3,623 140,687 12.
Number of Hours Reactor Was Critical 414.2 3.118.6 106.816.1 l
13 Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 411.6 2.858.2 101.842.8 l
15 Unit Reserve Shutdown Hours 0
0 0
~
16.
Gross Thermal Energy Generated (MWH) 993,087 6.692.616 208.326.255 17 Gross Electrical Energy Generated (MWH) 323,151 2,181.221 66.680.984 18.
Net Electrical Energy Generated.(MWH) 306.161 2.078.235 63.014.349 19 Unit Service Factor 55.3 78.9 72.4 l
l-20.
Unit Availability Factor 55.3 78.9 72.4 21.
Unit Capacity Factor (Using MDC Net) 53.3 74.3 58.0 22.
Unit Capacity Factor (Using DER Net) 51.8 72.2 56.4 23.
Unit Forced Outage Rate 44.7 21.1 12.6 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:
6-6-86
$$$$$o$k$Ico 7
N a
e OPERATING DATA REPORT DOCKET NO. 050-249 i
DATE June 2,1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.
Unit Name: Dresden III 2.
Reporting Period:
May, 1986 i
3 Licensed Thermal Power (MWt):
2 527
- 4. _ Nameplate Rating (Gross HWe):
ann 5
Design Electrical Rating (Net MWe): 794 6.
Maximum Dependable Capacity (Gross MWe): R12 3
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 8.estrictions, if Any: N/A This Month Yr-to-Date Cumulative 11.
Hours in Reporting Period 744 3,623 130,272 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)
-5,422
-24.865 55,701,429 19 Unit Service Factor 0
0 68.9 20.
Unit Availability Factor 0
0 68.9 21.
Unit Capacity Factor (Using MDC Net) 0 0
55.3 22.
Unit Capacity Factor (Using DER Net) 0 0
53.9 1
l 23 Unit Forced Outage Rate 0
0 12.4 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
j In 9th Refueling /RPR outane.
i 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
July, 1986 l
i
..---.,---,-..,-.--.---,.-,w-._,r.--
---,-wem..,ve,.
,e...~... - -, - - -. - -,,~
COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF May, 1986 HOUR MAXIMUM DAILY LOAD DAY ENDING KW i
1 1600 818000 2
2300 780600 3
0900 781200 4
1000 780500 5
2300 811500 6
0400
'814200 7
1300 814900 8
0300 811200 9
1300 814900 10 0100 810600 11 1700 812100 12 1100 810300 E13 1100 807200 i4 1500 806400 15 2400 807600 16 1000 809500 17 0600 806100 18 0100 177900 0
19 0000 20 0000 0
21 0000 0
22 0000 0
23 0000 0
24 0000 0
25 0000 0
26 0000 0
27 0000 0
28 0000 0
29 0000 0
30 0000 0
31 0000 0
L_
TI-'
j AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 UNIT II DATE June 2, 1986 COMPLETED BY D. C. Maxwell TELEPtiONt.,815/942-2920 MONTH May, 1986 DAY-
' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 767 17 678 2
742 18' 7
3 717 19 0
4 754 20 0
5 740 21 0
6 740 22 0
7 786 23 0
'8 777 24 0
9 768 25 0
10 762 26 0
11 756 27 0
12 770 28 0
13 777 29 0
14 767 30 0
15 773 31 0
16 765
T AVERAGE DAILY UNIT POWER LEVEL t
DOCKET NO. 050-249 UNIT III DATE June 2,1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH May, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Ne t) 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 O
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
~
r-<
c7, p--,---+---
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, -. +
DOCKET NO. 050-237' p UNIT NAM II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE June 2, 1986 s
COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920.
REPORT PR) NTH May, 1986 ETHOD OF LICENSEE CAUSE-& CORRECTIVE NO.
DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (BOURS)
DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE 5
.86-05-18 F
332:24 H
I Manually shutdown for drywell (332.4) snubber inspections and mainte-nance.
I 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)
(NUREC-0161)
E-Operator Training & License Examination F-Administrative 3
G-Operational Error
.(
H-Other (Explain)
DOCKET NO. 050-249 UNIT NAME III
-UNIT SHUTDOWNS AND POWER REDUCTIONS DATE June 2, 1986 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920.
REPORT MONTH Mav, 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 CODES PREVENT RECURRENCE 6
85-10-23 S
744:00 C
1 Off-line manually to 9th Refueling / Recirculation Pipe Replacement 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)
(NUREC-0161)
E-Operator Training & License Examination F-Administrative i
G-Operational Error H-Other (Explain) r
ni D1 F SO E*4 UNII 2 SAFEff.4FLATED H3tNTENA'sCE 84A TUHF Of-LER Oft OUT AGE
.1 A L FU*iC T 10's EQUIPMENT MAINTENANCE NUM;3 F R CAUSE.
RESULT CORDECTIVF ACTION CHKD AND CALIB. PS.2-2540-20.
U-2 CCCD COttPdFSSUR CORRECTIVE
'4/ A PE2-2540-20 W.St. 050025 2POM GROUP cl COR AC C TIVE N/A P511 OUTPUTS SET FOR POSITIVE / NEGATIVE W.R. 051631 20 VOLTS. REPLACED POWER SUPPLY UNIT.
02 OIESEL GENERATOR PRE VE N T IVE N/A PERF OR ME D 3 MONTH INSPECTIO*4 AS TO 2-6601
.W.R. 051650 PROCEDURE OMP-6600-2 REV.I.
Qu'4 7C8 CORRECTIVE N/A-
==
NO PROBLEM 03 SERVED $1NCE 03-18-86 MM2-753-7 C 8
..W.R. 0517F4 ACCORDING TO CECO ENG.'NO dORK PERFORMED FUEL POOL PAC MONITOR CHANNEL CORNECTIVE N/A
==---
REPLACE 0 GM TUSE IN DETECTOR. VERIFIED "t."
W.R. 053036 PROPER CALIHRATION OF ARM AND TRIP 2-1743-A SETPOINTS PER DCP2700-12 REV. 5.
2B MSIV PREVEr4TIVE N/A
=
==--- --
ADJUSTED PACKING PER WR.
2-203-23 W.R. 053177 20 MSIV PREVENTIV'E N/A ADJUSTED PACKING PER WR.
2-203-20 W.R. 053178 LPCI LOOP SELECT DIFFERENTIAL CORRECTIVE N/A REPL ACEO B40 MICR0 SWITCH. PERFORM
==----- = ---------
' PRESSURE SdITCH W.R. 053361 DIS 1500-9 REV. 3 DPI S 2-261-354 T0RUS WIDE R ANGE LEVFL TPANSMIT PREWFMTIVE P!/A REPL ACEO 0-RINGS ANO LUBRICATED AS PER LT-1641-5A C 1641-58 d.R. 053367 SP-86-1-18 REV.
O.
U2 HPCI 04AIN Lt*E CORRECTIVd N/ 4 TFMPORARLY REPAIR ELBOW UPSTRE AM OF 2-2323-1" LA 053524 VALVE J27 C J30. NEW ELn0W WILL SE 1*43TALLED UNDER d.R. 53552.
~
OdEiDEM.trat i 2 S*.FETV RELOTfD Mal %TE74AtKE -
N A TUR E OF Lfd OR OUTAGE MALFut!CTION EQU I PME'8 T MA t r4T E N ANCE NU%ER CauSE RESOLT
. CORRECTIVE ACT10:4 Put'ED TOP C bat TOM COVERS O'd LPCI HT.6N 23 LPCI HE A T EXCHA%ER
.CORRFCTIVE N/A 23 1533 W.R. D53526 04-28-86. PLUGGEO UNE'TUuE, REINSTALLED.LPRM 40-57C Do.dr4SC ALE LIGHT '
CURRECTIVE N/A MEPLACEO AMP FOR LPRM & CALIS. PER W.R.
D43M01 PROCEDURES.
13*4 PCE-AMP CURRECTIVE f4/ A '
=-
- - - =- -
REPLACEO PART Q12, VERIFIED GPERAT104.
2-750-23A13 W.R. D509d7.
BENCH TESTED AND OK.-
/
I 0
9 e
9 9xFSDE'4 Pr4I T 2/3 SAFETY RELATFD CINTE r.udCE NATUar OF LER OR OU T AG t.
MALFUNCTIO4 E3UIPMENT MAINTENANLr
. N U.<d f R CAUSE RESULT CORRECTIVE ACTION COSEFOUf4T PREiS. IPANS*ITTER CORRFCTIVE N/ A T R A'I S* 1 T T E 4 15 NON-REP AIR AoLE. T Ho od W.R. 0 3o2 69 AWAY S/N 251272. ROSEMJ14T PRE SSURE TRANS"ITTEk MODFL ll53DA3.
SdLC CELIEF SPARr VALVE CORRECTIVE N/A VALVE FOUND TO BE 6EYOND REPAIR.
W.R.
D40551 I
DISC ARDED V ALVE.
COS E MORP4T PRESS. TRANS.
PRFVENTIVE N/A REPLACED AMPLIFR. BOARD L CALIS. TO NAME SN/405100 W.R. D409M3 PLATE DATA USING ROSEMOUNT VENDOR'S M Ai4U AL.
MOV. 2/3-TED7-0 CURRECTIVE N/A.
REMovt0 LIMITORQUF. DISASSEMdLED AND W.R. 048214 CLEANFO ALL PARTS. INSPECTED PARTS.
RE-ASSEM6 LED LIMITORyUE USING NEW PARTS.
MOV. 2/3-T507A CORRECTIVE N/A
== -- -
REMOVED LIMITORCUE. DIS ASSEM3LE0/FOU:43 W.R. 048215 GREASE BLACK / RUNNY. CLEANED ALL AN3 INSPECTED. REASSEMdLEO USING NEW PARTS.
MOV-2/3-7505-3 CORRECYlVE N/A REMOVED LIMITORQUE. DISASSEM3tE0/FOUND W.R. 048216 GR E A SE GOLDI SH C OL OR. INSPECTED PARTS /
FOUND WORN GEAR. REPL ACE D WI TH NEW PARTS. REASSEM3 LED LIMITORQUE.
MJV-2/3-7505-A C UR RE C T IVE N/A RFNOVED LIMI TOROUE. DI S ASSEM,lLE D/FOU'49 W.R. 04871T GREA SE GOLDISH COLOR. CLE ANED ALL PARTS.
& FOUND WORM GEAR. REPLACED WITH NEW PARTS. REASSEM3tED LIMITORQUE.
- 0V-2/3 75 04-ti 03RRECTIVE N/A REMOVED Lt d IT040U9. DI SA SSEMSLED Af40 W.R. 04821M CLE ANED PART S. CHKD P ARTS. RE ASSEMSLED, REINSTALLFD.
MJV-2/3 7504A f.ORR F C T I VE N/A REMOVE 0 LIMITORQU9. DISASSE*0 LED A40 W.R. 048219 F OU'3D (,R E ASE PL ACK/Ruf4NY. CLEAR.E0 ALL &
REASSEMPLFO. REINSTALLEO.
G.E. A.R. :4. SE'4SnR CopRFCTIVE N/A REPL ACED C AP AC ITOR C 12 At40 C AL ISR A T ED W.R. 041944 AGR PROCLOURE.
C OdFSt,C*t it'4I T $
-5AftTY RELaTEJ :1 A irsIEls A 4C h 3
- {
NAitME OF led OR OUTAGC MALFUNCTION c Qu ! Pric':I "AINTLNANCF 40% E M CAUSE RESULT CnRR EC T I V E ' AC T 10.4 33 OliCH ARGd HDd. H '4 C094FCTIVei N/A
=--- ---------
REfflVf D OLO V ALVES LEAKING THRJ FLOOK
'VLV:3-1492-323 W.P. u142J3 ANO 14STALLEO.:4E4 VALVES AS.PER PKG AND,
+
PROC EDUR ES.
INSPECTED AND CAlleRATED PRESSURE TRANS-R*.E S. 50*? PRcs. TRANS P<FVENTIVE 4/A PT-3-1641-6A W.R.
04224%
MITTER PER PROCEDURE DIS 1600-1T REV.O PERFORM E.J.
If4SPECT10N.
CAM R AD OCTEC T04 PR E VF re T IVE N/A RE-3-24ted W.R. 042240 1
i C W4 RAO DETECTUR P d FV Ef4T IV E N/A PERFORM E.Q.
I NSPEC T late Cc-3-2418A W.R. 042241 i
O.u CO 4T AIN.tf r4T # AD. MON CORRECTIVE N/A RE PL AC ED INPUT SIGNAL CONNECTOR ANO 1
RM3 24199 W.R. 050101 PERFOR MED E.Q.
INSPECTION l
Cu'4T AIMMEf4T R AC '90NITOR CORRECTIVE N/A REPAIRED CONTAINMENT RAD MONITOR NUMBEM Rd3-24190 W.R. 050313 RM-3-2419-3 AND CALI6 RATED.
i SJLC RFLIEF VALVF CORRFCTIVE N/A
= - -
VALVE BENCH TESTED PER DMP-1100-2 RV-3-1tOS P W.R. 050455
\\
ACRJ-CAM INLt I CORRFCTIVE N/A
--~~ --
REPLACED DEFECTIVE SPAN POT C CALloRATED t
FLOd SCJARE FOOT E X T R AC T OR W.R. 050988 PER PROCEDURES.-
3-2540-25 P I
MAI4 STtAM LI:4E L OG R AD Md4.
CORMELTIVE N/A
- - - - - - - - -=
dEPL ACED R142 & CALIB. LRM, CHECKFu 3-I F05-2A W.R. 053022 AL ARMS AND REL AY OPER A 10f4 VIA APPLICABLE SECTIONS OF OIS 1700-1, REV.T.
i 3
"3" SOLC JISCH HE4DLR CURRECTIVE N/A
--=
TIGHTEN COUPLING TO PREVENT LEAKINo.
3-1102-1 1/t" w.R. 053510
04f S0tr4 Utili )
SAFETY RE L ATEO 74 A lte T F N AF4C E NATURF Of LtR GR OUTAGE MALFUtiCTION L'J O I P*t t'I T MAINTENANCE NU"6ER CAUSL PESULT CORREC TIVE ACTION PLUGGEO 21 TUBLS ACCUROING TO TU 3r MAP.
3 ":_" LPCI HEAT F x0ei A4GE R COPAFLTIVE
'f/ A 3S-1503 W.P.
053626 PLUGt,ED TOP AND BOTTdM OF TU3ES.
REoOILT A *O CHECKFU PER PROCEDURES.
CLEUILD SPARE ILr C TROM A T IC CURRECTIVE N/A 2/3-203 S/N BA 7049 W.R. 044022 RESUILT ANU CHECKED PER P R('CE DUR L S Ct3OILD SPARE ELFCTROMATIC CORRECTIVE N/A
=--
--- =
2/3-233 S/N ftK 70531 W.R.
044021 CALIBRATED TEST LLRT BOX PtR PROCf00RE OTS-31 LLRT BOX PREvFNTIVE N/A W.R.
053640 DIP 2100-8 DTS-32 LLRT PUX PREWFNTIVE N/A CALTBRATED TEST LLRT 80X PER PROCEDURE W.R.
D93641 DIP 2100-8
1 s.-
r.
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 which relief valve was actuated, how it was actuated, and the circum-stances resulting in its' actuation.
l Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2
05-01-86 to 05-31-86 None q
3 05-01-86 to 05-31-86 None
s
SUMMARY
OF OPERATING EXPERIENCE UNIT Th'0 MAY, 1986 M
05-01-86 to 05- -86 Unit 2 e'ntered the. month operating at maximum core flow and operated until 5-18-86 at 0336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> when 3
the turbine was manually taken off~1ine for a planned inspection of the drywell snubbers. The reactor was manually made sub-critical at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> of the same morning. The unit stayed off-line the remainder of the month for maintenance.
Capacity factbr for the month was 52.08% and availa--
bility was 55.32%.
I i
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p-g g b9 4
-,s.
+y T
SUMMARY
OF OPERATING EXPERIENCE UNIT THREE MAY, 1986 05-01-86 to 05-31-86 Refueling outage activities continued throughout the entire period. The unit is presently scheduled to startup in July, 1986. Major work includes:
- Normal pump (s) and valve (s) maintenance
- ISI inspections
- LLRT
- ILRT preparations o
}
O Telephone 815/942-2920 Commonwealth Edison Dresd9n Nuclear Power Cation RR.#1 Morris. Illinois 60450
)
June 2, 1986 j
DJS LTR:
86-385 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 May, 1986. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.
Sincerely,
/
D.
. 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 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 INPO Records Center File /NRC Op. Data File / Numerical h
i i