ML20005G477
| ML20005G477 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/31/1989 |
| From: | Diederich G, Thunstedt J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9001190210 | |
| Download: ML20005G477 (26) | |
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- 8" I Commonwealth Edison LaSalD County Nuclear S; tion
.- Rural Route C1, Box 220 -
Marseilles, Illinois 61341
. Telephone 815/357-6761 t
Tu ,
January 10, 1990 !
I 1
i Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission ;
i Mail-Station Pl.137 q Washington, D.C. 205$5 i ATIN Document Control Desk f Gentlemen:-
! Enclosed for your information is the month 3y performance report covering LaSalle County Nuclear Power Station for December,1989. f i
, Very truly yours, ,
' t M
. J. Diederich
-k'[StetionManager '
LaSalle County Station f GJD/JW7/sjj
'i' Enclosure xc A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle Ill. Dept. of Nuclear Safety l P. Shemanski, NRR Project Manager '
D. P. Galle, CECO D. L. Farrar, Ceco INPO Records Center -
L. J. Anastasia, AIP Coordinator, Nuclear Services J. E. Kuskey, GC Resident T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Fuel Services Manager
- C. F. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station T. A. Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff Supervisor Central File ZCADTS/5 7 9001290210 991233 --
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT DECEMBER 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11
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TABLE OF CONTENTS !
I. INTRODUCTION F
I II. REPORT
- t.
i A.
SUMMARY
OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS,' EXPERIMENTS, AND SAFETY RELATED MAINTENANCE l' 1. Amendments to Facility License or Technical Specifications
- 2. Changes to procedures which are described in the Safety Analysis Report '
- 3. Tests and Experiments not covered in the Safety Analysis Report
- 4. Corrective Maintenance of Safety-Related Equipment
- 5. Completed Safety-Related Modifications
- C. LICENSEE. EVENT REPORTS ,
D. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
- 1. Main Steam Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of Failed Fuel Elements l
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! 1. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each I unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat.ls 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 One was issued operating Ilcense number NPF-11 on April 17, 1982.
Initial criticality was achieved on June 21, 1982 and commercial power
- operation was commenced on January 1, 1984.
t This report was complied by John W. Thunstedt, telephone number l' (815)357-6761,- extension 2463.
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m, II. MONTELY REPORT A. SUMKARY OF OPERATING EXPERIENCE
- Day Ilma Event 3 0000 Reactor subcritical, generator off-line, L1R03 in progress.
31 2400 Reactor subcritical, generator off-line, L1R03 in progress.
B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.
- 1. Amendments to the Facility License or Technical Specification.
Removal of cycle-specific parameters
- 2. Changes to procedures which are described in the Safety Analysis Report.
LLP-89-058 " Loss of Power to Bus 242Y with Tailure of D/G 2A to Start or Load" This proceudre provides a method of crosstying the "1A" D/G to Bus 242Y via the Unit-tie breakers 1424 and 2424 to provide backup emergency AC power to Bus 242Y via the "1A" D/G as required by Technical Specification during an extended "0" D/G outage with Unit 2 at power.
- 3. Tests and Experiments not described in the Safety Analysis Report.
(None)
- 4. Major corrective maintenance to Safety-Related Equipment.
(See Table 1)
- 5. Completed Safety-Related Modifications.
(See Table 2) 4 ZCADTS/5
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' O.4 TABLE 1 1 a
MAJOR CORRECTIVE MAINTENANCE *IO SAFETY-RELATED EQUIPMENT WORK REQUEST RESULTS AND EFFECTS .
NUMBER COMPONENT CAUSE OF MALFUNCTION- ON SAFE PLANT OPERATION CORRECTIVE ACTION (Unit 0) (None)
(Unit 1)
L94701 1AP-04E Dirty Contact Breaker would not close Replaced HACR (control) y 0 D/G Output Breaker relay L94877 IE22-5001 Piping Crack Oil Leak (spray) Replaced fitting HPCS:D/G fuel-oil filter L95610 Drywell Personnel Seal. Failure Air leakage Replaced seals Air-lock, Inner Door Drive Shaft l
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,. 00dPLETED SAFETY-RELATED MODITICATIONS !
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NUMBER DESCRIPTION M01-1-87-096 Replace the existing RPS and PCIS reactor water level switches with an analog trip system consisting of Rosemount level i transmitters and trip units. e s-Temporary System Change 01-87-89 Installed a temporary Electrical Teed from Unit 2 Division I to L Unit 1 Division I to provide power to the 'O' D/G Immersion l" l heater, AC Soakback pump, Oil Circulating pump, and Generator i Space heater to allow these loads to perform as designed during ;
the Unit 1 Division I Battery Modification.
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e Work Request L94283 " Locking the '1B' Diesel Generator Governor Run Solenoid for Troubleshooting"'
Locking the governor run solenoid in the run position does not prevent the DG from performing its design function, however it will prevent a shutdown of the engine only, on differential overcurrent and the emergency stop button. This is because the i engine trips are initiated by the lockout relay via the run solenoid. This will not affect the D/G output breaker and the engine. The overspoed trip is not affected because the .
overspeed is a total mechanical function that prevents the fuel injectors from supplying fuel. All other engine and breaker trips with the exception of differential overcurrent, '
overspeed, and emergency stop are bypassed in an ECCS Condition.
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.- C LICENSEE EVENT REPORTS y.
Lgk Numher M Descrit> tion Correction to the previous (November 1989) report 7te event reported as LER $89-028-00 (dated 11/22/89) was determined not to be an LER prior to its submittal to the NRC. This number will be re-issued to the next reportable event to maintain sequential numbering.
l^ 89-028-00 12/04/89 Shutdown Cooling Outboard isolation valve
(~ auto-closure due to communication error during instrument surveillance.
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D. DATA TABULATIONS
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- 1. Operating Data Report (attached) l- 2. Average Daily Unit Power Level (attached)
- 3. Unit Shutdowns and Power Reductions (attached) l l
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D.i L OPERATING DATA REPORT- 00Ct:ET NO. 050373 UNITLASALLECWE DATE Janasty to, 1990 COMPLETED BY J.W. THUNSTElii TELEPHONE (815) 357-6761 OPERATIE STATUS
- 1. EPORTING PERIOD: = ECEMER 1989 GROSS HDURS IN REPORTING PERIOD: 744
' 2;'CURRENTLYAUTHORIZEDPOWERLEVEL(Wt): 3,323 MAX M PEND CAPACITY (HWe-Net): 1,036 DEEIGN ELECTRICAL RA11NG ( We-Net) 1,078
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) ( We Net): 0
- 4. REASONS FOR ESTRICTION (IT ANY)t Refseling (L1R03)
. EPORTING PERIOD MTA THIS MONTH YEAR-TO-MTE CUMULATIVE
- 5. TIME REACf0R CRITICAL (HOURS) . 0,0 6,114.8 32,134.1
- 6. TIME REACTOR RESERVE SHUTDOW (HOURS) 0.0 0.0 1,641.2
- 7. f!E GENERATOR ON-LIE (HOURS) 0.0 6,103.8 31,418.3 B; TIME GENERATOR RESERVE SHUIDO N (HOURS) 0.0 0.0 1.0
- 9. THERMAL EERGY GEERATED '(MWHi-Gross)- 0 19,054,990 87,833,568
- it ELECTRICAL' ENERGY GEERATED (WHe-Gross) 0 6,422,787 29,068,541 Lit. ELECTRICAL ~ EERGY GEERATED (WHe-Neil -7,605 6,157,173 27,732,702
- 12. REACTOR SERVICE FACTOR (I)- 0.0 69.6- 61.1
- 13, REACTOR AVAILABILITY FACTOR (!) 0.0 69.6 64.2
- 14. SERVICE FACf0R (%) 0.0 69.5 59.7 E 15. AVAILIIILITY FACTOR (1) 0.0 69.5 59.7
- 16. CAPACITY FACTOR (USING MDC) (%) -1.0 67.7 50.9 A
- 17. CAPACITY FACTOR (USING ESIGN We) (I) -0.9 65.0 48.9
'18. FORCED OUTAGE FACTOR (!) 0.0 1.4 10.1' l
- 19. SHUTDOWNS SCHEDULED DVER THE NEKi 6 MONTHS (TYPE, DATE, AND DURATION OF EACHb j (None)
- 20. IF SHUTDOWN AT END OF REPORT FERIOD, ESTIMATED DATE OF STARTUP:
January 05,1990
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E. UNIQUE REPORTING' REQUIREMENTS 1., Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIK ACTUATED E2DATION CWDITLW OF EVENT i, (None) i-
[ 2. ECCS System Outages L
I- QUIAGE NO. EQUIPMENT FURPOSE (Note the year and unit numbers have been ommitted from the Outage Number) l F- .IUnit_Q) ~(None)
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- (Unit 1)
E' -1603 LPCS Spool Piece Remove 1606' 1DG024 Repair seat 1633 1E22-C002 (DG) Trouble-shoot motor 1647 LPCS/LPCI Perform LTS-800-104, 500-19 1676 1E12-F016A(RH) Install containment-spray spool piece 1684 1B D/G Replace motor 1692 1E12-F099A/B (RH) Perform LOP-NB-01 1659 Div. I Drywell spray Install ILRT spool piece 1710 "0" D/G ODG01K Check / replace crankcase pressure switch 1717 Head Spray Install jumper piping 1721 RCIC Steamline Drain Replace double block 1E51-F052/F053 s
-1728 100014 Disassemble, clean 1744 EFCV, IE12-F359B (RH) Flush
'1747 EFCV, IE12-F359B (RH) Repair 1751 1G33-F042 Repack 1753 1A D/G Hydrolate cooler 1754 1A D/G (Various EM work) 1756 1E12-F024B (RH) Perform LOP-RH-07 ZCADTS/5
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c;(, ; 1777' U-1-ECCS_ Systems. ILRT-jp .n ' i g 11789 Div-II RHR SW (Administrative) l 1801 Drywell Spray- Remove ILRT Spool 'f i
1809. 1C RHR Cy Fill Perform LOP-RH-16 l
1830 'A RHR 24, 27 Shutdown-Cooling Operations .
i 3.-- .Changesit o the Off-Site Dose Calculation Manual- ;
(None). {
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- 4. Major changes to Radioactive Waste Treatment Systems. !
lt~ (None)
- 5. Indications of Failed Fuel. Elements. '
.(None)'
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!s LASALLE NUCLEAR POWER STATION !
UNIT 2 .;
MONTHLY PERFORMANCE REPORT DECEMBER, 1989 is .
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- COMMONWEALTH EDISON COMPANY i
NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 -
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TABLE OT CON'"ENTS I
I. INTRODUCTION I 1
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)
II. REPORT 1 A.
SUMMARY
OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED ;
f MAINTENANCE I
- 1. Amenemonts to Facility License or Technical Specifications
- 2. Changes to procedures which are described in the Safety .
j Analysis Report. i
- 3. Tests and Experimente not covered in the Safety Analysis Report. ;
- 4. Corrective Maintenance of Safety-Related Equipment '
- 5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
- 1. Operating Data Report i
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions .
E.- UNIQUE REPORTING REQUIREMENTS l 1. Safety / Relief Valve Operations ]
1
- 2. ECCS System Outages
- 3. Of f-Site Dose Calculation Merzwal Changes )
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of railed Fuel Elements l
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- 1. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit f acility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each s
unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste 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 prinary construction contractor was Commonwealth Edison Company.
Unit Two_ was issued operating license number NPT-28 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 John W. Thunstedt, telephone number (815)357-6761 extension 2463.
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. .. II. MONTHLY REPORT o .,
[ A.
SUMMARY
OF OPERATING EXPERIENCE Day Ilme Event 1 0000 Reactor critical, generator on-line at 3325 MWT.
9 2300 Reduced load to 2618 MWT for routine surveillances.
10 1900 Returned to full power.
13 0200 Reduced load to 1075 for CRD exercising.
1000 Returned to full power.
17 0000 Reduced load to 2130 MWT for Heater-Bay and "A" Turbine-Driven Reactor Feed Pump repairs
18 1000 Returned to full power.
30 2100 Reduced load to 2034 MWT for rod-setting and steam leak repair.
2300 Began slow ramp to full power.
31 1900 Steady at 3060 MWT, held per Load Dispatcher.
2400 Reactor critical, generator on-line at 3060 MWT for Load Dispatcher.
B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTEN ANCE.
- 1. Amendments to the Facility License or Technical Specification.
Removal of cycle-specific parameter limits.
l 2. Changes to procedures which are described in the Safety t j Analysis Report.
(None) 1 f
ZCADTS/7
3.. Tests ~and Emperiments not dos rlbed-13 the 5:fGty' Analysis
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Report.
(N ne)f 4.. Major corrective maintenance to Safety-Related Equipment.
(None)
Additionally, beginning this month, 80R switch failures will be reported separately from Nuclear Work Request reporting; see p -attached data sheets regarding the failure of 2B21-NO38B and 2E22-N006.
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- 5. Completed Safety-Related Modifications,
,f-(See Table 2) f-l l
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,. EQP do Switch Failure Data Sheet j s
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Equipment Piece. Number ZB2L-KQ201 Model Number:.lQ1- g-1211-N'X-JJTTX6-h Serial Numbert EL-12-spjl ,
' Application: Reactor Vessel Lov Water Level- 3 ADS Permissive Switch !
l Date and Time of Discovery - LL/21/01 Q12Q hours fi
.. . i Reactor Mode: ! L. - Power Levels 1QQ},
- Calibration Tolerances. Elti-223dfWC f
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Nominal Setpoint: 63478'WC j p Action. Limits: ~ <1&ul or >61tl?WC j
. Reject' Limits: <EhdQ or >ElugfWC l I
h 1 Technical Specification
- Limits- </= 64.84'WC -j g
h 'Jnr Found Setpoint: EZuQ'WC f i
Date.and Time of Return to Services' LL/21/Q12Q11 hours Model. Number of Replacement =Switcht' 1Q1-E-8211-EX,-JJTTX6 .
1 Serial Number of Replacement Switch: gg-L-lgll ,
Causes Instrument Setooint Drift
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Corrective Action: Replaced lov veter level switch and inspection of failed ;
switch found no abnormalties '
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i i Deviation Report: 1-2-89-069
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Equipment Piece. Number: 2[22,-HQQ5. Model Number LQ.2,-E-BB202-E'-JJTTX6
. Serial Number: 66,-2.*2s&1
. Application:' Hinh Pressure Core Sormy Minious Flow Switch 1
Date'and Time of Discovery: 11/12/61 ZQQ1 hours
' Reactor Mode 1 Power Level LQQ.1.
.. Calibration Tolerance: 22d-22.d* WC -
' Nominal'Setpoint:- i~ '
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22d'WC -
l '4 - 5 Action Limits:.
<21d orf >Zis.2.'WC
' Reject-Limitsi. (22d or >2fd*WC Technical Specification Limits. 9. 7 + /- L,,,Q2,' WC As Found Setpoint's 2fd'WC Date and: Time of Return to Service: LL/lf/0,2,122), hours i
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Model Number of Replacement Switch: LQ2-E-BB202-E-JJTTX6
' Serial Number of Replacement Switch -QS.-LQ-iQsi [
Cause: ' Instrument Setooint Drift I
t Corrective' Action:
abnormalties found Replaced switch and insoected failed switch with no i i
_ Deviation Reports. 1-2-89-067 i l'. ,
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MODIFICATION N , yttmara oggegyp7ygg M01-2-86-002 Removal of the NSSS supplied racks and install high density free standing spent fuel racks for the Unit 2
(. Spent Fuel Storage Pool.
i M01-2-86-057 Roslope the cross tie drain on line 2HG060A-6" to the suppression pool to improve flow and to allow proper drainage.
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. C.- LICENSEE EVENT REPORTS LER Mumber Date Description 89-018-00 12/16/89 250 VDC Battery Electrolyte Temperature Low
} 89-019-00 12/26/89 RCIC High-Level Trip Switch Failure.
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p-D. DATA TABULATI0 tis
- 1. Operating Data Report (Attached) I
- 2. Average Daily Unit Power Level (Attached) )
- 3. Unit Shutdowns and Power Reductions (Attached) l l
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D.i DPERATING MTA REPORT- DDCKET NO. 650-374 UNii LASALLE TWO MTE Jarmary 10, 1990 COMPLETD BT J.W.THJNSTD T TELEPHDNE (Bl5F357-6761
.OPERATINGSTATUS
~ 1. EPORTING PERIOD: KCEDER 1909 GROSSHOURSINREPORTINGPERIOD: 744
,2. CURENTLY AUTHORIZD POKR LEVEL (MWth 3,323 NAX DEPEND CAPACITY (MWe-Neth 1.036 K SIGN ELECTRICAL RATING (MWe-Net) 1,07B
! 3i PoutR LEVEL TO WHICH RESTRICTD (IF ANY) (MWe-Neth (None)
- 4. REASONS FOR RESTRICTION (IF ANih (N/A)
REPORTING PERIOD MTA THIS MONTH YEAR-TO-DATE CUMULATIVE
- 5. TIME REACTOR CRITICAL (HOURS) 744.0 6,669.1 30,147.1 6i TIE REACTOR RESERVE SHUT 90WN (H0l3S) 0.0 0.0 1.716.9
,7. TIME GENERATOR DN-LIE (HOURS) 744.0 6,592.1 29,683.1 8 TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0
9. - TERMAL ENERGY GEEtATO (M!i-Gross) ~ 2,412,040 20,380,440 86,320,048 10, ELECTRICAL ENERGY GENERATO (MWHe-Cross) ,
825,671 6,747,588 20,450.926
' 11. ELECTRICAL ENERGY CENERATD (Nie-Net) 797.050 6,496,055 27,235,305
- 12. REACTOR SERVICE FACTOR (!) 100.0 75.9 66.1 13; REACTOR AVAILABILITY FACTOR (I) 100.0 75.9 69.0
- 14. SERVICE FACTOR (!) 100.0 75.0 65.1
- 15. AVAILIPILITY TACTOR (!) 100.0 75.0 65.1
,16. CAPACITY FACTOR (USING MDC) (1) 103.4 71.4 57.6
- 17. CAPACITT FACTOR (USING DESIGN MWe) (!) 99.4 68.6 55.4 IF FORCD OUTAGE FACTOR (!) 0.0 14.2 16.3 P
- 19. SHUTDOWNS SCHOULD DVER THE NEXT 6 MONTH $ (TYPE, DATE, AND DURATION OF EACH):
Refseling(L2R03) 03-17-90 12 Weeks
-20.-IF SHUTDOWN AT END OF REPORT PERIOD, ESilhAID DATE OF STARTUP:
(N/A)
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LWii LASALLE TWO
,~' LD.2~AVERAGEDAILYUNITPOWERLEVEL(MWe-Net) - DATE January 10, 1990
-c. COMPLETED BY J.W. THUETEDT s
(- TELEPHONE (815)-357-6761 1 REPORTPERIOD: ' DECEMBER 1989' m
DAY- ' POKR . BAY POWER'
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b -1 1,105 17 ~ 875 ,
2 .1,101 18 1,077 3- 1,101 19 1,092 -
~4- 1,105 20 1,077
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,' y: .5 1,103 - 21 1,088 6- 1,093 22 1,081
('" ' ?. 1,103- ~23 . 1.089 8 1,103 - 24 1,091
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9 ,1,097 ~ 25 ~ 1,093-10 - 1,008 ; 26 1,090
.11 1,,097 27 1,072
' 12 1,095 28 i,063
' 13 - 1,086 29 1,063 -
14 . ' i,098 30 1,012 15- i,097 31 915 ss 16 1,041
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4 .. e METHOD OF _ SHUTTING DONN YEARLY TYPE ~ CORRECTIVE-DURATION THE REACTOR OR SEQUENTIAL F: . FORCED - ACTIONS /COBOEENTS
' REASON CODE' REDUCING ~ POWER NUMBER DATE S: SCHEDULED (HOURS)
' B -: 5 _ Miscellaneous routine 9 S 0.0~
33 .surveillances.
-5 CRD exercising
- 0. 0 .. B 34 13 S B 5~ Heater-bay and "A" 5 0.0 35 17 TDRFP repairs B 5 Rod-set and steam leak.
36 30 S 0.0 ' repair. ZCADTS/7 _
, -: C. ;E.- . UNIQUE REPORTING REQUIRD4ENTS
.. ; n ., e
- y. ; 1. 5 foty/R311of.Volv0 Op3rctions
-y , VALVES' NO & TYPE- ~ PLANT DESCRIPTION-
. DATE AC'!UATED ACTUATICMS CCMDITICE OF EVENT
'(N o ne ) -
1 7. ECCS' System Outages-OUTAGE._ liq,. EQUIPMENT PURPOSE
- NOTE: The year and unit designators have been omitted from the Outage Number.
-1040- 2B RHR Pump Lubricate, replace oil
'1041 -2A D/G Clean Strainers
.1042 HPCS Pump- Replace' oil t.;
L1- '1053 2A RHR Pump Replace oil
,1055 2B D/G Replace 2E22-N504 1056- 2B D/G Lubricate 1057 2B D/G Motor- Replace high-pressure vent assembly.
Driven Compressor 1061: '2E22-C302A (DG) . Replace head gasket 1068 2DG059 Check "B" Compressor Operation n
- 1069 2A D/G "A" Repair oil' leak Air Compressor
'3.- . Changes to the Off-Site Dose Calculation Manual
, (None).
~4. Major changes to Radioactive Waste Treatment Systems.
- (None)
- 5. Indications of Failed Fuel Elements.
(None) ZCADTS/7 J}}