ML20045A972
| ML20045A972 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/31/1993 |
| From: | Cialkowski M, Spedl G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306150414 | |
| Download: ML20045A972 (21) | |
Text
{{#Wiki_filter:m, q-2 LCcmmenwacith Edison i .s LaSalle County Nuclear Station RuralRoute #1, Box 220 t Marseilles, Illinois 61341 Telephone 815/357-6761 June 11, 1993 1 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C. 20555 ATIN: Document Control Desk Gentlemen: l 1 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for May 1993. -I Very truly yours fg ') Gary F pedl Station Manager LaSalle County Station Enclosure l ac: A. B. Davis, NRC, Region III l D. E. Hills, NRC Resident Inspector LaSalle l J. L. Roman, IL Dept.- of Nuclear Safety D. Stransky, NRR Project Manager M..J. Wallace, CECO l D. L. Farrar, CECO INPO Records Center i D. R. Eggett, NED P. D. Doverspike, GE Resident T. K. Schuster,. Manager of Nuclear Licensing T. A. Rieck, Nuclear' Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor M. P. Pietryga, QA/NS Off Site Review Station File I T@"< k ) / 9306150414 930531 i . PDR ADOCK 05000373 tjy P DR --
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y ~ h LASAT.T.E NUCLEAR PONER STATION UNIT 1 MONTHLY PERFORMANCE REPORT MAY 1993 COMM33fEALTH EDISON CO(PANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 h l 1 -I 1
i TABLE OF CONTENTS (UNIT 1) I. INTRODUCTIN II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. AMMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATICMS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETT-RELATED EQtJII' MENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS 1. Operating Data Report 2. Average Daily Unit Power Level 3. Unit Shutdowns and Power Reductions l F. UNIQl1E REPORTING REQLIIREMENTS 1. Main Steam Safety Relief Valve Operations 2. ECCS System Outages 3. Of f-Site Dose Calculation Manual Changes 4. Major Changes t.o Radioactive Waste Treatment System 5. Indications of Failed Fuel Elements ? b
i l I. INTRODUCT101 (UNIT 1) The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Maste 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 contractor was Commonwealth Edison Company. Unit one was issued operating license 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. This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427. I b I
- 11. M3tTHIJ REPORT 1
A. SIDWARY OF OPERATING EKPERif2fCE (Unit 1) Day Tlac Event I 0000 Reactor critical, Generator on-line at 1125 Mwe. 0100 Reduced power level to 1090 Mwe due to system load. i 0900 Increased power level to 1125 Mwe. 2 '0100 Reduced power level to 850 Mke due to system load, performed rod set. 3 1100 Increased power level to 1125 Mwe. 4 0030 Reduced power level to 850'Mwe due to system load. 1230 Increased power level to 1125 Mwe. I 6 0200 Reduced power level to 850 Mwe due to system load. l 0900 Increased power level to-1115 Mwe. i 2300 Reduced power level to 700 Mwe due to loss of the 15A l Feedwater heater noomal drain valve. 7 1100 Increased power level to 1115 Mwe. I 9 0030 Reduced power level to 950 Mwe due to system _ load. ..i i 0400 Reduced power level to 850 Mwe due to system load. 1300 Increased power level Lo 1120 Mwe. 3 10 0100 Reduced power level-to 850 Mwe due to system load. l 0900 Increased power level to 1115 Mwe. -f i 11 0100 Reduced power level to 850 Mwe due to system load. j 0900 Increased power level to 1115 Mwe. 13 0030 Reduced power level.to 850 Mwe due to system load. 1 0900 Increased power level to 1125 Mwe. i f 14 0300 Reduced power level to 1000 Mwe due to system load. 1200 Increased power level to 1125 Mwe. 15 0300 Reduced power level to 950 Mwe due to system load. 1100 Increased power level to 1120 Mwe. i i m.
II. MOITIILY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1) May Time Eyent 16 0100 Reduced power level to 900 Mwe due to system load. 1200 Increased power level to 1120 Mwe. 17 0200 Reduced power level to 850 Mwe due to system load. 0900 Increased power level to 1122 Mwe. 18 0200 Reduced power level to 850 Mwe due to system load. 0800 Increased power level to 1120 Mwe. 19 0300 Reduced power level to 850 Mwe due to system load. 0800 Increased power level to 1120 Mwe. t 20 0100 Reduced power level to 1000 Mwe due to system load. 0800 Increased power level to 1120 Mwe. 21 0200 Reduced power level to 1000 Mwe due to system load. 0800 Increased power level to 1120 Mwe. 22 0230 Reduced power level to 850 Mwe due to system load. 1100 Increased power level to 1120 Mwe. 23 0300 Reduced power level to 850 Mwe due to system load. 1100 Increased power level to 1120 Mwe. 24 0200 Reduced power level to 850 Mwe due to system load. 0900 Increased power level to 1120 Mwe. 25 0300 Reduced power level to 900 Mwe due to system Joad. 1000 Increased power level to 1125 Mwe. 26 0100 Reduced power level to 850 Mwe due to system load. 1000 Increased power level to 1125 Mwe. 27 0200 Reduced power level to 900 Mwe due to system Joad. i 1000 Increased power level to 1125 Mwe. l l
J I II. MONTHLT REPORT A.
SUMMARY
OF OPERATING EKPERIENCE (Unit 1) Day Ilme Kygnt 28 0130 Reduced power level to 850 Mwe due to system load. 1000 Increased power level to 1125 Mwe. 30 0400 Reduced power level to 900 Mwe due to system load. 1130 Increased power level to 1120 Mwe. 31 0300 Reduced power level to 850 Mwe due to system load. 1200 Increased power level to 1125 Mwe. 2400 Reactor critical, Generator on-line at 1050 Mwe, power level being reduced due to system load.
D. AMMENTMENTS *JD THE FACILITY OR TECHNICAL SPECIFICATI N (None) C. MAJOR CORRECTIVE MAINTENANCE "10 SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports). (See Table 1) D. LICENSEE EVENT REPORTS (Unit 1) (None) E. DATA TABULATIWS (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) F. UNIQUE REPORTING REQUIREMENTS (UNIT 1) 1. Safety Relief Valve Operations (None) 2. ECCS System Outages Note: The year and unit data has been removed from the outage number. ( OTTEAGG U0, C001k%CWE L'UiWDSC G443 1E22-S001 Repair jacket water temperature sensing line and air start valves. 0446 1E22-C302B Valve repair. 0457 IE12-COO 3 Replace MCC contactor. 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) l i i l 1
1 C. TABLE 1 (Unit 1) MAJOR CORRECTIVE MAINTENANCE TO SAFETT-RELATED EQUIPMENT WORE-RESULTS AND EFFECTS REQUEST _CChnct.n l CAUSKJI_104BJNCTION QN_ SAFE PLANT OEERATlQti CORRKC[IVEJCTlDi L22628 Intermediate Range Voltage pre-regulator Inaccurate readings Replaced voltage Monitor Channel A pre-regulator L22710 Source Range Voltage Pre-regulator Inaccurate readings Replaced voltage Monitor Channel B pre-regulator (No SOR failures this month.)
. ~ - k-j i TABLE 2 E.1 OPERA 7ING DATA REPORT DOCKET NO.- 050-373 UNIT LASALLE ONE. i DATE June 11, 1993 _j COMPLETED BY M.J.CIALKOWSKI i OPERATING STATUS TELEPHONE (815) 357-6761 1. REPORTING PERIOD: May 1993 . GROSS HOURS IN REPORTING PERIOD: 744 i 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078 3 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A { 4. ' REASON FOR RES'IRICTION (IF ANY): t THIS MONTH ' YEAR TO DATE CUMULATIVE 5. REACTOR CRITICAL TIME (HOURS) 744.0 2,782.2 56,706.9 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 5 7. GENERATOR DN-LINE TIME (HOURS) 744.0 2,512.8 55,420.4 8 UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 9. THERMAL ENERGY GENERATED (MWHL) 2,342,523 7,609,598 162,669,756
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 786.911' 2,542,541 54,334,890 i
11 ELECTRICAL ENERGY GENERATED (MWHe-Net) 760,809 2,443,346 52,091,436 i 1 l
- 12. REACTOR SERVICE FACTOR (%)
100.0 76.8 68.7 l 1
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0 76.8~ 70.7 i '14. UNIT SERVICE FACTOR (%) 100.0-69.4 67.1 { 1
- 15. UNIT AVAILIBILITY FACTOR (%)
100.0 69.4 67.1 'I6. UNIT CAPACITY FACTOR'(USING MDC) (%)- 98.7 65.1 60.9 { -17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 94.9 62.6 58.5.
- 18. UNIT FORCED OUTAGE FACTOR (%)
0.0 .13.7 7.2 i i -19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS ( TIP E, DATE, AND DURATION OF EACH) 2 'i .No Outages Scheduled -20i IT SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 4 i a
= - -. TABLE 3 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DOCKET NO. 050-373 j UNIT LASALLE ONE DATE June 11, 1993 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 I e i a REPORT PERIOD: May 1993 l i DAY POWER DAY POWER 4 1 1,055' 17 1,032 1 2 836 18 1,029 3 1,013 19 1,025 e C 4 1,016 20 1,057 l -? 5 1,083 21 1,057 6 994 22 998 7 953 23 1,008 4 8 1,074 24 1,031 1 9 985 25 1,044 f 10 1,019 26 1,019 3 Il 1,011 27 1,046 -]. 12 1,069 28 1,022 13 1,019 29 1,076 14 1,061 30 1,032 15 1,050 31 1,004 i 16 980 i t -. j i i - i i .a s t i t
I I TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% (UNIT 1) METHOD OF CORRECTIVE YEARLY TIPE SHUTIING DOWN ACTIOfS/CO94ENTS St>Jurm11AL DATE F: FORCED DURATICH THE REACIOR OR (LER/DVR I if NUMBER IID4MDDJ S1_It.mmQIED IIIQURSl._ REASON REDUCING _PSHER cpplic hl3) (None)
SUMMARY
OF OPERATION: The unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to system loading, maintenance and surveillance activities.
i t LASALLE NUCLEAR POWER STATICM UNIT 2 NCMTHLY PERFORMANCE REPORT MAY 1993 CO>OKENEALTH EDISCM CCMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 I -6 l I e
r TABLE OF COfTENTS (UNIT 2) 1. INTRODUCTION II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. AMMENDMENTS 'ID FACILITY LICENSE OR TECHNICAL SPECIFICATICMS C. MAJOR CORRECTIVE MAINTENANCE *IO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TAHULATIONS 1. Operating Data Report 2. Average Daily Unit Power Level 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS 1. Main Steam Safety Relief Valve Operations 2. ECCS System Outages 3. Off-Site Dose Calculation Manual Changes 4. Major Changes to Radioactive Maste Treatment System 5. Indications of Failed Fuel Elements i r i
I. INTRODUCTION (UNIT 2) The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. f Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Maste heat is rejected to a man-made cooling pond using the I]Iinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Cornmonwealth 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 October 19, 1984. This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427. f ? f h ) F i v r i
II. MOfTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 2) DDy 7119C KYDAt 1 0000 Reactor critical, Generator on-line at 1127 Mwe. 4 2330 Reduced power level to 850 Mwe, performed monthly surveillances and rod set. 5 1100 Increased power level to 1130 Mwe. 16 2330 Reduced power level to 850 Mwe due to system load, and performed rod adjustments. 17 1400 Increased power level to 1120 Mwe. 28 2300 Commenced power reduction for maintenance outage. I 29 0800 Generator off-line. 1100 Manual reactor scram. 31 2400 Reactor sub-critical, generator off-line, maintenance outage in progress. I e P [ k 4 w f i 1 I
t B. AMMENDMENTS *10 THE FACILITY OR TECHNICAL SPECIFICATICH I (None) [ C. MAJOR CORRECTIVE MAINTENANCE 'IO SAFETY-RELATED EQlJIPMENT (None) SOR differential pressure switch failure reports (None) D. LICENSEE EVENT REPORTS (Unit 2) ? 1&ILNumber Date Description r 93-003-00 05/24/93 Spurious auto st_ art of the 'O' Diesel [ Generator, 2A Low Pressure Core Injection and the Low Pressure Core Spray pumps during surveillance testing. E. DATA TAINJLATIGIS (Unit 2) f 1. Operating Data Report (See Table 1) 2. Average Daily Unit Power Level (See Table 2) 3. Unit Shutdowns and Significant Power Reductions (See Table 3) f F. UNIQlIE REPORTING REQUIREMENTS (UNIT 2) i 1. Safety Relief Valve Operations f (None) 2. ECCS System Outages (See Table 4) 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)
4 TABLE 1 -J ~ E.1 OPERATING DATA REPORT j ..a DOCKET NO. 050_373 J UNIT LASALLE Tdo DATE June 11, 1993 i COMPLETED BY M.J.CIALKOWSKI l OPERATING STA*IUS TELEPHONE (815) 357_6761 ]
- 1. - REPORTING PERIOD:
May 1993 GROSS HOUIIS IN REPORTING PERIOD: 744' - 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEliDABLE CAPACITY (MWe-Net)t 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078 l - 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A J 4. REASON FOR RESTRICTION (IF ANY): l THIS MONTH YEAR TO DATE CUMULATIVE i 5. REACTOR CRITICAL TIME (HOURS)' 683.0 3,562.0 54,575.5 -{ 6. REACTOR RESERVE ~ SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9-7. GENERATOR ON-LINE TIME (HOURS) 680.0 3,559.0 53,615.4. 1 I 8. UNIT RESERVE SIRITDOWN TIME (HOURS) 0.0 0.0 0.0 9. THERMAL ENERGY GENERATED (MWHL) 2,218,956 11,494,081 161,508,968
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 751,428 3,908,447 53,809,756.
II. ELECTRICAL ENERGY GENERATED (MWHe-Net) 726,242 3,778,973 51,691,906
- 12. REACTOR SERVICE FACTOR (%)
91.8 98.3 72.2 [ i - 13. REACTOR AVAILABILITY FACTOR (%) 91.8 98.3 74.5
- 14. UNIT SERVICE FACTOR (%)
91.4 98.2 71.0 l - 15. UNIT AVAILIBILITY FACTOR (%) 91.4 98.2 71.0
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
94.2 100.7 66.0 l . 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 90.6 96.8 63.5 l ~
- 18. UNIT FORCED' OUTAGE FACTOR'(%)
0.0 0.0 11.9 i 1 l
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS ( TIPE. DATE, AND DURATION OF EACH):
Refuel, 09/04/93,--11 Weeks .{ - 20. IT SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 06/06/93 1 1 J 4..i b. ..r-.. _,-.m,
3 -, * ~ TABL5 2 E.2 . AVERAGE DAILY UNIT PGNER LEVEL'(MWe-Net) l DOCKET NO. 050-373' l UNIT LASALLE TWO' 1 DATE June 11, 1993. l COMPLETED BY M.J. CIALKOWSKI i TELEPHONE (815)-357-6761 { i 'I i REPORT PERIOD: May 1993 .l DAY POWER DAY POWER l 1 1,086 17 1,007 f 2 1,084 18 1,083 a { 3 1,086 19 1,085 4 1,064 20 1,085 I ^i .1 l 5 1,014 21 1,085 6 1,083 22 -1,086 7 1,s33 23 1,086 8 1,085 24 1,087 [ -9 1,082 25 1,088 .i f 10 1,082 26 1,088 I 11 1,076 27 1,087 12 1,075 28 1,084 13 1,081 29 116 + -i 34 1,083 30 _12 .i 15 1,083 31 -12 i 16 1,060 i 6 1 4 l 'i i b s t'
' TABLE 2 j E,2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DOChET NO. 050-373 l UNIT LASALLE TWO j DATE June 11, 1993 -l COMPLETED BY M.J. CIALKOWSKI TELEPHONE-(815)-357-6761 3 l s, i REPORT PERIOD -May 1993 i DAY POWER DAY POWER i i 1 1,086 17 1,007 -i' 2 1,084 18 1,083 } 3 1,086 19 1,085 4 1,064 20 1,085 5 1,014 21 1,085 6 1,083 22 1,086 t 7 1,083 23 1,086 I 8 1,085 24 1,087 i 9 1,082 25 1,088 10 1,082 26 1,088 11 1,076 27 1,087 12 1,076 28 ',084 i 13 1,081 29 i 14 1.083 30 .-12 35 1,083 31 -12 l 16 1,068 k - I E I.: 4 I i F t
k 4 TABLE 3 E.3 UNIT SHUTDONNS AND FONER REDUCTIONS > 20% (UNIT 2) METUOD OF CORPECTIVE YEARLT TYPE SHUTTING DONN ACTIONS /CCMMENTS Srwur.nfiAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR I if NUMBER IIYMMDDJ St _S_N LUp]RSl_ RF M REILUXING POWER applicahle) 1 930529 5 64.0 B 2 Maintenance outage i i l SUle4ARY OF OPERATION: The unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, maintenance and surveillance activities. On 05/29/93 the unit entered a scheduled maintenance outage and remained off-line for the remainder of the month.
i (UNIT 2) '~.- Table 4 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number. RUTAGE_NQ1 MXIIIMD!I PUEEDS5 0351 2E12-C300C Valve inspection. 0352 2E12-C300D Valve inspection. 0353 2E12F003B Valve inspection. 0377 2E22-C003 Heplaced pump. 0423 2E12-D300A Replace backwash line.}}