ML20086M119
| ML20086M119 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/30/1991 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9112170225 | |
| Download: ML20086M119 (25) | |
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/ Tc!0 phone 815 / 3573 N1 December 10, 1991 Olrector of Nuclear Reactor Regulation United States Nucicar Regulatory Comission Mail Station PI-137 Hashington, D.C. 20555 AllN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering LaSalle County Nuc1 car Power Station for November, 1991.
Very truly yourt.,
s G. J. Diederich r#(Station Hanager LaSalle County Station GJD/HJC/djf Enclosure xt: A. B. Davis, NRC, Region III T. H. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuc1 car Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L farrar. CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T, J. Kovach, Hanager of Nuclear Licensing H. f. Nanghton, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor H. H. Servoss. QA/NS Off Site Review Station file a 1217o275 9111'::o PDR fiDOC t: 0500'073 R PD9 ZCADTS/5
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i LASALLE NUCLEAR F0HER STATION UNIT 1 HONTHLY PERf0RKANCE REPORT NOVfMBER 1991 COHHONWEALTH EDISON C(HPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l
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TABLE Of CONTENTS (UNIT 1)
- 1. IN1RODUCTION II. REPORT A. SUHHARY Of OPERATING EXPERIENCE B. AHENDHEN15 10 FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPOR1S E. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENfS
- 1. Main Steam Relief Valve Operatisms
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Haste Treatment System
- 5. Indications of failed fue) Elements l
ZCADTS/5
I. INTRODUCTION (Unit 1)
The LaSalle County Nuclear Power Station is a two-unit facility owned by Comonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Bolling Hatqr Reactor with a designed net electrical output of 1078 Hegawatts. Hast9 heat is rejected to a man-made cooling pond using the Illinois Rivet fN ne'. -up and blowdown. The architect-engineer was Sargent and Lundy A & r,limary construction contractor was Comonwealth Edisen C wp t r, Unit One was issued myr.ittng license number NPF-11 on April 17, 1982.
Initial criticality en uhteved on June 21, 1982 and comercial power operation was cowaert 96 u January 1,1984.
This report was cehod by Michael J. Cialkowski, telephone number (815)357-6761, er ternion 2/127.
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II. MONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Day Time Event 1 0000 Reactor critical, generator on-line at 1125 Mwe 9 0400 Reduced power IcVe1 to 1000 Mwe due to system load.
1200 Increased power level to 1130 Mwe.
12 0200 Reduced power level to 850 Hve for maintenance activities in the licater bay.
0400 Increased power level to 1080 Mwe.
1100 Increased power level to 1130 Mwe.
15 0200 Reduced power level to 920 Hwe due to system load.
1400 Increased power level to 1130 mwe.
17- 0830 Reduced power level to 1075 Mwo to transfer the Condensate / Condensate Booster pumps.
1400 Increased power level to 1130 Mwe.
19 0130 Reduced power level to 1000 Mwe to perform monthly surveillances and to perform a rod set.
0830 Increased power level to 1130 Mwe.
20 2200 Reduced )ower level.to 900 Hwe to remove the
'IB' Turaine Driven Reactor feed Pump from service for seal replacement.
21 0600 Increased power level to 950 Mwe (power level held due to '1B' Turbine-Driven Reactor feed Pump out of service).
23 0100 Reduced power level to 880 Mwe due to system load, m 0830 Increased power level to 1000 Mwe.
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' 0230 Increased power level to 1130 Mwe.
26- 0910 Reduced power. level to 1080 Hwe to transfer the Heater Drain pumps.
1800 Increased power level to 1130 Mwe, r
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II. HONTHLY REPORT (Continued)
A. SUHKARY Of OPERATING EXPERIENCE (Unit 1)
Day Time Event 27 1130 Reduced power level to 1075 Hwe to transfer the Heater Drain pumps.
1800 Increased power level to 1130 Hve.
29 0230 Reduced power level to 850 Hwe due to systm. load.
1200 Increased power level to 1130 Hve.
30 0100 Reduced power level to 850 Hwe due to system load.
1500 Increased power level to 1130 Hwe.
30 2400 Reactor critical, generator on-line at 1130 Hwe t
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, 8. AMENDHENTS TO THE TACILITY LICENSE OR TEGINICAL SPECIf! CATION Position of the Nuclear Regulatory Conselssion in regardt, to inter-granular stress corrosion cracking in boiling water reactors.
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C. HAJOR CORRLCTIVE MAINTENANCE TO SAFETY-RELATED EQUIPHENI' (in:1uding SOR differential pressure switch failure reports).
(See Table 1, D. LICENSEE EVENT REPORTS (Unit 1) l LULRumttfI QAtt QUIL{ption _
91-015-00 11/07/91 Inability to confirm testing of certain undervoltage relay contacts on Safety Division 1, 2 and 3.
E. DATA TABULATIONS (Unit 1)
- 1. Operating Data Report (See Table 2)
- 2. Average Daily Unit Power Level (See Table 3)
- 3. Unit Shutdowns and Significant Power Reductions (See Table 4) 4 ZCADTS/5
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C. TABLE 1 (Unit 1) .
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT ,
RESULTS AND EFFECTS HORK RE00EST CORRECTIVE ACTION COMPONENT CAUSE OF HALFUNCTION ON SAFE PLANT OPERATION NUMBER Supply air filters dirty. High differential pressure Replaced air filters LO5316 OVE01FB Aux Electric Equipment Room HVAC across filter.
Filter Broken weld on damper Damper unable to open. Revelded damper linkage.
L11277 OVC11YA Control Room HVAC Inlet Damper linkage.
Nitrogen accumulator valve None. Replaced valve.
L11428 Hydraulic Control Unit 50-35 leakage.
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(No SOR Failures this month.)
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1AllE 2
- I.! ONRA11NG N'A REFORi 10CffiND.0$N7)
ON111A%Ltl OK t MIE te:nter 10. 1991 :
00Milif t if M.J. CI Alt 0V%I l I
TELEF G C (015)*357-4761 f
f DMf6Tik0$1ATUS li REPORTING M ilDru bater 1971 U055110!% IN KffkilNG FER10th 720
- 2. CURRENTLf AliTHORIED . IWF R t[Vit (Mth 3,323 Mt KKND CMACITY tMarath 1,9%
K51t* Elicit! CAL PAi!NG (MeNeth 1,078 34 POWER LEVEL TO usICH K51RIC)ED tlf Am (Newth N/A
- 4; FEACDNS TOR EESTRitT100lf Asth .
llP0Ai!NG MP10D MTA
...... - . ~ ........ . ~ ... ... ~ .........., ...
1HIS $0 NTH MAF10-DATE CUMut AllVL - t t
15.- EACTOR CRll!CA!,11hl Wkts) 720,0 6,M3,1 46,612.5' ,
- 6. KAC10R ICLEAVE SHUID00W 11hC lkDURS) 6,0 0.0 1,641,2
- 7. GDtilA10R ON-LINE ilnE uiOURS) 720.0 5,0!i5.6 45,634.4
'0.' tiNil RESERVE SHU1ITN4 TIMI Ot00R$) - 9.9 0.6 1,0 -
9, THEE K ENEF&f GENERATED (NHti 2,317,744 19,550,769 132,754J70 13, ELECTRICAL ENEkDT KNIRATED (MJHe4mu 794,005 6463,1M 44,266,454 .
Lit. ELEC1klCAL ENERBf 6EERAllt (MirNet) 769.013 6,928,872- 42,M8.974
- 17 3 fAC10R SEM ICE TACTOR (U 100.0 14.9 (7,2 -
,13. EACID9 MAILA!!Litt f ACTOR (U 100.0- 74[9 69 5 11eiUNITGEIVICEFACTOR(U 100.0 73.4- 65.7 3
- 15. UN!1 AVAILIEILITY FACTOR (U IM.0 73.4 65.9 =
l16. INIT CAPAClif FACTOR (U$ING MK) (U 103.1 - 72.6 59.0
17.~ 0N11 CAFACITY f ACIOR (US!kG Kilte Ne) (U Y9.1 67.0 - 56,7 f dB, ilNil TOPCED 001 AGE Fact 0R 41)- 0.0 2.5 ' ~17 19.ES*f'TDOWS SOOJLEB'0VCR THE NEXI 6 ft0#THS (IfK,' Mii, AND 10kAlJON DT EACH)!
29, IF SHUTDXN AT EkD Dr kEPORT KR10D, E$TIMIED MIE Di STAETUP.
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- i 10(t!1 ND. 050 373 Im[] LNilL G al04
[.2 Ad F AUL ! Alt f t41f 00V!P lEV{t (MueNeti IAll DH tite r 10,1Fil C',*ftllt! 11 n.J. ClkJ 0.Skl IELEld;sE (815)-357-(741 l[f0kl ((ilCL; Np.st!tr !?il Lty '0iEE IA f 00a!A
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1 I d'i7 17 1,092 2 1,0,7 19 1,(V9 3 f.101 19 1.677 4 1,103 20 1,005 5 1,102 21 928 6 1,102 2; 9 69 7 1,1l.2 ;'3 944 8 1,105 24 9,'O 9 1,095 Ta 1,0!1 16 1,0'/ 9 26 1,067 11 1,095 27 1.100 12 1,047 26 1,104 13 1,09? 27 1,015 t
14 1,096 3) 1.026 15 1,065 31 16 1,100
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e TABLE 4 E.3 UNIT SHUTD0hNS AND PONER REDUCTIONS > 207. '.
(Unit 1) ,
METHOD OF COiLRECTIVE YEARLY TYPE SHUTTING DOHN ACTION 3/CGNENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD) S: SCHEDJLED (HOURS) REASON REDJCING PONER applicable)
(None.)
SUNHARY OF OPERATION:
The Unit remained ,m -line at high power throughout the montt.. Sevcral minor power reductions were required di.e to system loading, meintenance activities and routine surveillances.
ZCADTS/S
F. UN100E REPORTING RtQUIREMENTS (Unit 1)
- 1. Safety / Relief valve operations VALVES NO & TYPE PU.NT DESCRIPTION QAIL ACTUATED ACJUAILQM CONDITION Of_EMI_
(None)
- 2. ECCS System Outages (See lable 5)
- 3. Changes to the Off-Site Dose Calculation Manual (None.)
- 4. Major changes to Radioactive Haste Treatment Systems.
(None)
- 5. Indications of failed fuel Elements.
(None)
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(Unit 1)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number GUBGE_R02 faU1V_EEI E1LRE0SE (U-0) 2054 ODG08CA Repair check valve.
2055 (U-1) 2016 1E12-C3000 Coupling lubrication.
2017 IE12-C300C Coupling lubrication.
2038 1E12-C002A Lubrication.
2040 ZCADTS/5+
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LASALLE NilCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 4
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TABLE OF CONTENTS (Unit 2)
I. INTRODUCTION II. REPORT A. '
SUMMARY
OF. OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT s
,0. LICENSEE E','ENT REPORTS E. DATA TABULATIONS .
1.= Operating Data Report
-2.
Average Daily Unit Power Level 3.- Unit Shutdowns and Power Reductions ,
F.- UNIQUE REPORTING REQUIREMENTS
- 1. . Safety / Relief Valve Operations
> 2. ECCS System Outages . .
-3. Off-Site Dose Calculation Manual Changes 4.. ' Major. Changes to Radioactive Haste Treatment System Indications of failed fuel Elements v
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' I. INTRODUCTION (Unit'2)
The LaSalle' County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies,-Illinois. Each unit is a Bolling Mater Reactor with a designed net electrical output of
-1078 Megawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. 'The architect-engineer was Sargent and-Lundy and the primary construction contractor was Commonwealth Edison Company.
-Unit Two was: issued operating-license number NPF-18 on December 16, . - -
- 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.
This report was compiled by Michael-J. Cialkowski, telepho u 'number (815)357-6761--' extension 2427.
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4 II. HONTHLY REPORT A. SUHKARY OF OPERATING EXPERIENCE (Unit 2)
Day Time Event 1 0000 Reactor critical, generator on-line at 136 Hwe.
0235 Reactor critical, generator off-line due to steam leaks discovered during the ramp to power.
0918 Generater on-line.
1425 Increased power level to 280 Hwe.
1818 Increased power level to 378 Hve.
2026 Increased power level to 507 Hwe.
2050 Increased power level to 605 Hwe (power level held due to high vibration readings on turbine bearing
- 0).
2 0310 Increased power level to 1060 Hve.
2300 Increased power level to 1095 Hwe.
3 2200 Reduced power level to 750 Hwe to perform rod set.
4 011$ Increased power level to 878 Hwe.
0200 Increased power level to 1050 Hwe.
0730 Increased power level to 1120 Hwe.
6 2400 Reduced power level to 1042 Hwe to transfer the Condensate / Condensate Booster pumps.
7_ 2000 Reduced power level to 900 Hwe to remove the
'2A' feedwater pump from service.
8 0600 Placed the '2A' feedwater pump in service, increased power level to 1070 Hwe.
1300 Increased power level to 1127 Hwe.
13 2350 Reduced power level to 1020 Hwe for Electro-Hydraulic Control testing.
14 2345 Increased power level to 1120 Hwe.
ZCADTS/7
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,[?II. MONTHLY. REPORT (Continued): j A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 2)
Day Time- Event 16 1000 Reduced power level to 1060 Hwe to tra!. fer the Condensate / Condensate Booster pumps.
1430 Increased power level to 1120 Hwe.
2315 Reduced power level to 1070 Hwe to transfer the Condensate / Condensate Booster pumps.
17 1100 Increased power level to 1120 Mwe.
2400 Reduced power level to 850 Hve to perform Turbine Control Valve testing.
18 0730 Increased power-level to 1090 Hwe.
1300 Increased power level to 1120 Mwe.
20- 0300 - Reduced power level to 1000 Hwe to insert control '
rod 42-11 due to accumulator problems.
0800 Increased power level to 1090 Mwe.
p 22 0110 Reduced power level to 750 Mwe for rod set.
0530 Increased power level to 1060 Hwe.
1000 Increased-power level to 1120 Mwe.
30 2400 Reactor critical,-Generator on-line at 1120 Mwe.
ZCADTS/7
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R. AMENDNENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION Position of the Nuclear Regulatory Commission in regards to inter-granular stress corrosion cracking in holling water reactors.
C.. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPMENT (including SOR differential- pressure switch failure reports).
(See Table-1)
D. LICENSEE EVENT REPORTS (Unit 2)
LER_MushtI Dale Qgscription (None.)
E. DATA TABULATIONS (Unit'2) i
- 1. Operating Data Report.
(See Table 2)-
- 2. Average Daily Unit Power Level.
(See Table 3)
- 3. Unit Shutdowns and Significant Power Reductions.
(See Table 4) l i
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.C.. TABLE 1-(Unit 2); "
MAJOR CORRECTIVE MAINTENANCE TO
> SAFETY-RELATED EQUIPMENT NORK REQUEST .
RESULTS AND EFFECTS .
NUMBER COMPONENT .
CAUSE'OF MALFUNCTION _0N SAFE PLANT OPERATION CORRECTIVE ACTION-
- L11103 Division'2 Post-LOCA. Heat trace temperature Degraded analyzer output. . Replaced temerature' ;
H2/02 Analyzer switch. - switch. }
L11349 ; Control. Rod. Drive- . Time delay. relay. Relay' failed calibration. Replaced relay. '
Charging Hater Header !'
Pressure-c;
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f (No SOR Failures this month.) !
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1ABLE 2 E.1 Of1 FATING DATA FEPORT DOCLET N0. 050-374 UNil LA5ALLE TWO MIE December 10,1991 C0r.PLETE D FY h,J. C!ntt0GI TELEhiDNE (215)-357-6761 Of'ERMINS SI A10S
- 1. IfPORTINGffRIOD: Nr m.ter 1991 ER055 H3URS IN RE!0RilNG PERIOD: 720 2, CURRENTLf AUlh0kilED l'0JER LEVEL But): 3,323 MAX IEFEND CAFACITt Mae' Net): 1,036 If 51EN ELECIFICAL FAllND GWe-Neth 1,07B
- 3. POWER LEVEL TO WHICH I. 01E1? tIf ANY) tNe-Neth WA
- 4. RfA50!G FDR EESitIEl10N (If ANi):
FEPORTING PEF 10D IAf A THIS nJhTH YE AR-TO-MIE CUM A ATIVE
- 5. EEACTOR CRITICAL ll C (H0025) 720 6 7 701.6 44,191.8 6, PEACTOR F.ESERVE SRJTD005 IInE (HOURS) 0.0 0.0 1,716.9
- 7. GEhERATOR ON-LINE ilhE 00.T5) 713.3 7,613.4 43,460.6
- 8. UN11 RESEEVE SHUTDOWN TlhE (HOURS) 0.0 0.0 9.0
- 9. THERMAL ENfRGY GENERATED (Git) 2,277,667 24,4E2,995 127,922,170
- 10. ELECTRICAL ENER6f GENERATED RWHe-Ensu 767,32{ 9 2 '.,054 43.105,986
- 11. ELECTRICAL ENIRGf GENERATED (Nde-Net) 74],077 7.954,50 41,373,657
- 12. REACIOR SERVICE TACIOR (X) 100.0 ill 70.8
- 13. PEACIGR AVAlt.ABIllif FACTOR (t) 100.0 96.1 716 10 UNIT SERVICE FACIOR (%) ?? I 95.0 69.6
- 15. UNIT AVAlli!!!LITf FAciO2 ix) 99.1 95.0 69.6 16, UNIT CAPACITf TA0109 (USINC MDC) (%) 99.6 95.8 64,0 17, LHit CAPACITY FACIDE W3140 X$IGN huta (%) 95.7 92.1 61.5
- 18. Usil FGRCED cutAC4 F ACTOR (1) 0.9 5.0 13.3 E SHUT 37a3 SCHEDAED C'KR RE NEXT 6 KNTn5 (TifE, EATE, AND DjfATION Of EACH):
REFUELING (L2R64) 01/04/92 11 UEEKS
- 20. Ir SduiDCUN AT Ed 0F REPORT PERIOL ESTIMAlED MIE Of 51 A?iUF:
N/A
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l R O EI NO 050-374 1 AR f. 3 vN11 LA5ALLE 100 E.2 MEWi NILY LNIT F0WER LE'JEL (NMht) MTE Enener 10,1991 COVLETED El n.J. CIAtr005tl TELEhiDC (B15)-357-f?61 REP 0n1 PE910D: Nov ater 1971 I'AY POUER Mt POWEP 1 196 1? 1355
. 977 18 V72 3 1,006 ? .H4 4 1,029 '91 5 1,066 6 1 k!S t' 7 1,051 23 1,0d, 8 1,031 24 1,033
% 1,084 25 1,M9 10 1,63? :6 1,036 11 1,085 27 1,039 12 1,036 3 1,087 13 1,083 27 1,087 14 1,050 3) 1 ,0133 15 1,GS3 31 16 1,079
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TABLE 4 -
E.3 UNIT SHUTDOWNS AND Pot *ER REDUCTIONS >20%
(UNIT 2) .
METHOD OF CORRECTIVE SHUTTING DOWN ACTIONS / COMMENT 5 YEARLY TYPE DURATION THE REACTOR OR (LEE /DVR # if SEQUENTIAL DATE Fs FORCED (HOURS) REASON REDUCING POWER em>l1 cable) l NUMBER (YYMMDD)_ 5: SCHEDUIED l
F 6.7 A 4 Turbine Generator off-line to 5 911101 repair steam leaks (Reactor remained at approximately 6%
power).
SUNY OF OPERATION:
The Unit experienced a forced outage on 11/01/91 to repair steam leaks discovered during the ramp to power following the completion of the outage of 10/29/91. The Unit was returned to service on 11/01/91. The unit remained on-line at high power for the remainder of the sonth. Several minor power reductions were required due to system loading, maintenance activities and routine survelliances.
ZCADTS/7
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F. UNIQUE REPORTING REQUIREMENTS (Unit 2)
- 1. . Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION p_A_T1 LCTUATED ACTUATIONS CONDITION OF EVf3.T (Hone.)
- 2. ECCS System Outages (See Table 5.)
- 3. Changes to the Off-Site Dose Calculation Manual.
(None.)
- 4. Major changes to Radioactive Haste Treatment Systems.
(None)
- 5. Indications of Failed fuel Elercents.
(None)
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(Unit 2)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
00TAGE NQ,. E M PEEtLI P1BEOSE 2030 2E51-F046 Install torque switch.
2049 2E12-C300A Coupling lubrication.
2050 2E12-C3008 Coupling lubrication.
2052 2E12-F048A Inspection and limitorque rebuild.
2059 2053 2E12-F087A Inspection and limitorque rebuild.
2058 2054 2E12-F006A Valve testing.
2069 2E12-F048A Administrative control, 2071 2E12-C3008 Meggar motor.
2072 2E12-C300A Meggar motor.
2084 2E12-C300C Coupling lubrication and meggar 2085 2E12-C300D motors.
2088 2E12-F026B Valve testing.
2089 2DG08CB Valve inspection.
2104 2E22-C002 Coupling lubrication and meggar 2105 motor.
2106 2E22-C302A Inspection.
ZCADTS/7
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