ML20082K076
| ML20082K076 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/31/1995 |
| From: | Cialkowski M, Ray D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9504190062 | |
| Download: ML20082K076 (18) | |
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i Commonwealth Edison Company laidle Generating Station 2(dll North 21st Road Marseilles, 11.61341-97P Tel 815 35T61 l
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April 12,1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering
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LaSalle County Nuclear Power Station for March,1995.
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D. J. Ray i
Station Manager LaSalle County Station DJR/mkl Enclosure cc: John B. Martin, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C.
GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File 1 e r r e r-U.:. d
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oSO4190062 950331 f, p/
PDR ADOCK 05000373 3
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A l'nicom Compan) y I
LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT March 1995' CCDe00NNEALTH EDISON COMPANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11 i
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TABLE OF CONTENTS (UNIT 1)
I.
INTRODUCTION II.
REPORT A.
SISedARY OF OPERATING EXPERIENCE i
B.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.
LICENSEE EVENT REPORTS l
D.
DATA TABL't.ATIONS 1.
Operacing Data Report j
2.
Average Daily Unit Power Level 3.
Unit shutdowns and Power Reductions E.
UNIQUE REPORTING ICQUIREMENTS 1.
Main Steam Safety Relief Valve Operations 2.
Major Changes to Radioactive Waste Treatment System 3.
Static O-Ring Failures 4.
Off-site Dose Calculation Manual Changes t
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I.
INTRODUCTION (UNIT 1) 1 l
The LaSalle County Nuclear Power Station is a two-Unit facility owned l
by Commonwealth Edison company and located near Marseilles, Illinois.
l Each unit is a Boiling Water Reactor with a designed not 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 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 l
commercial power operation was commenced on January 1, 1984.
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This report was compiled by Ndchael J.
Cialkowski, telephone number (815)357-6761, extension 2056.
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l II.
MONTHLY REPORT A.
StBe4ARY OF OPERATING EXPERIENCE (Unit 1)
Day Time Event 1
0000 Reactor critical, Generator on-line at 1135 Mwe.
3 2300 Reduced power level to 1000 Mke for performance of a rod set.
4 0200 Increased power level to 1140 MWe.
5 1000 Reduced power level to 1060 NWe for performance of a rod set.
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1100 Increased power level to 1140 MWe.
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15 2200 Redu;ad power level to 850 MWe to perform Nkin Steam Isolation valve limit switch testing.
I 16 1000 Increased power level to 1140 Mwe.
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l 28 1000 Reduced power level to 850 NWe for maintenance on the f
14A Feedwater Heater normal drain valve.
2300 Increased power level to 1140 Nke.
l 31 2400 Reactor critical, Generator on-line at 1140 Nke.
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S.
AMENDNENT3 TO THE FACILITY OR TECHNICAL EPECIFICATION j
on March 16, 1995, the Nuclear Regulatory Cossaission issued Amend'aent No. 102 to Facility Operating License No. NPF-11 for:LaSalle County j
j Station Unit 1. The amendment is in response to the application dated october 24,,1994.
The. amendment restructures the primary containment and primary containment leakage technical specifications to reduce the repetition 1
of those requirements contained in NRC regulations such as Appendix J j
to 10 CFR Part 50. The amendment also supports requested exemptions I
j from Appendix J requirements related to the scheduling of containment integrated leak rate tests. In addition to the restructuring and scheduling changes, the amendments incorperates the relocation of the j
list of primary containment isolation valves in accordance with Generic Letter 91-08 and a revision to the interval for functional testing of j
hydrogen recombiners in accordance with Generic Letter 93-05.
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SUBNITTED LICENSEE EVENT REPORTS (Unit 1) i j
Occurance LER No.
Date Description J
95-002 02/07/95 The Reactor Core Isolation Cooling system was 1
out of service for maintenance. Af ter 1
maintenance was completed, the 1E51-F063 valve-i was closed for depressurising of the steam line, j
The line failed to depressurize. The 1E51-F063 4
valve was declared inoperable and valve l
1E51-F000 was taken out of service closed to comply with Technical Specification 3.6.3. The Reactor Core Isolation Cooling system was i
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declared inoperable per Technical Specification i
3.7.3, and a 14 day time clock was entered.
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95-005 02/08/95 New Diesel Fuel coming onsite at LaSalle was not j
tested per ASTM O2276 as specified in Technical j
specification 4.7.1.1.2.C.2.
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95-006 02/10/95 Technical Specification 3.3.6 requires a control j
Rod withdrawal block for the Reactor i
Recirculation system flow unit upscale, in operating and comparator trip. The procedure 1-which functionally tested these on a monthly I
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basis did not ensure the relays enforcing the j
rod blocks change state, j
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95-007 02/16/95 Quarterly surveillance for the Division III DC system was not performed as required by t
Technical Specification 4.9.2.3.1.B.1.
j 95-000 03/01/95 on 02/28/95 the daily control room temperature reading per Technical Specification 4.7.7 was
- j not taken in accordance with procedure LOS-AA-82 due to the unit 2 temperature monitor 2TM-VP105 being out of service. Temperatures were taken j
immediately on 03/01/95 utilizing the unit 1 temperature monitor 1TM-VP105, and were found to j
be satisfactory.
J D.
DATA TABULATIONS (Unit 1) 1.
Operating Data Report (See Table 1)
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2.
Average Daily Unit Power Level (See Table 2) i 3.
Unit Shutdowns and Significant Power Reductions (See Table 3)
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UNIQUE REPORTIN3 REQUIREMENT 3 (UNIT 1) 1.
Safety Relief Valve Operations (None) i 2.
Major Changes to Radioactive Waste Treatment Systems i
(None) 3.
Static 0-Ring Failures
-(None) 4.
Changes to the Off-Site Dose Calculation Manual (None) l i
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l TABLE 1 D.1 OPERATING DATA REPORT DOCKET No. 050-373 UNIT LASALLE ONE DATE April 10,1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 OPERATING STATUS 1.
REPORTING PERIOD:
March 1995 GROSS HOURS IN REPORTING PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 MAX DEPEND CAPACITY (MWe-Net):
1,036 DESIGN ELECTRICAL RATING (MWe-N 1,078 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
4.
REASONS FOR RESTRICTION (IF ANY):
5 REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE 5.
REACTOR CRITICAL TIME (HOURS) 744.0 2,029.7 68,669.6 i
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REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7.
GENERATOR ON LINE TIME (HOURS) 744.0 2,019.7 67,130.9 8.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 l
9.
THERMAL ENERGY GENERATED (MWHt) 2,451,662 6,536,765 199,223,590 j
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- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 835,464 2,224,394 66,615,285
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 813,835 2,159,062 63,928,206
- 13. REACTOR SERVICE FACTOR (%)
100.0 94.0 69.6
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0 94.0 71.3
- 14. UNIT SERVICE FACTOR (%)
100.0 93.5 68.1
- 15. UNIT AVAILIBILITY FACTOR (%)
100.0 93.5 68.1 7
- 16. UNIT CAPACITY FACTOR (w?!NG MDC) (%)
105.6 96.5 62.6
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%)
101.5 92.7 60.1
- 18. UNIT FORCED OUTAGE FACTOR (%)
0.0 6.5
- 8.2
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
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- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP:
DOCKET NO. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)
DATE April 10,1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 l
l REPor;T PERIOD:
March 1995 DAY PCWER DAY POWER l
1 1,091 17 1,098 2
1,095 18 1,099 3
1,094 19 1,101 4
1,091 20 1,103 5
1,095 21 1,102 l
6 1,099 22 1,102 1
7 1,100 23 1,102 8
1,099 24 1,102 9
1,100 25 1,099 10 1,101 26 1,101 11 1,102 27 1,102 i
12 1,103 28 994 13 1,102 29 1,100 14 1,102 30 1,101 15 1,095 31 1,099 16 1,036
TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 1)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS CEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NILI@_E_R IIYNNDD1 St SCHEDUIJ_Q (HOURS)
REASON REDUCING POWER aonlicable)
(None)
SUBEGARY OF OPERATION:
The unit remained on-line at high power throughout the month. Several minor power reductions were required due to maintenance and surveillance activities.
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4 LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT March 1995 CotesONNEALTH EDISON COMPANY NRC DOCKET No. 050-374 LICENSE No. NPF-18
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TABLE OF CONTENTS l
(UNIT 2)
I.
INTRODUCTION
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l II.
REPORT A.
St.DedARY OF OPERATING EXPERIENCE B.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.
LICENSEE EVENT REPORTS D.
DATA TABULATIONS 1.
Operating Data Report i
I 2.
Average Daily Unit Power Level 3.
Unit Shutdowns and Power Reductions E.
UNIQUE REPORTING REQUIREMENTS 1.
Main Steam Safety Relief Valve Operations 2.
Major Changes to Radioactive Waste Treatment System 3.
Static O-Ring Failures 4.
Off-Site Dose Calculation Manual Changes 1
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I.
INTRODUCTION (UNIT 2)
The Lasalle County Nuclear Power Station is a two-Unit facility owned by Conunonwealth Edison Company and located near Marseilles, Illinois. Each 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 contractor was Conunonwealth Edison Company.
Unit two was issued operating license number NPF-18 on December 16, 19P3. Initial criticality was achieved on March 10, 1984 and conmaercial power operation was comunenced on October 19, 1984.
This report was compiled by Michael J.
Cialkowski, telephone number (815)357-6761, extension 2056.
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II.
MONTHLY REPORT 9
A.
SIDedhRY OF OPERATING EXPERIENCE (Unit 2) 1 l
Day Time Event 1
0000 Reactor sub-critical, Generator off-line. Refuel outage (L2R06) in progress.
31 2400 Reactor sub-critical, Generator off-line. Refuel outage (L2R06) in progress.
B.
AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION On March 16, 1995, the Nuclear Regulatory Comunission issued Amendment No. 87 to Facility Operating License No. NPF-18 for LaSalle County Station Unit 2. The anwedmont is in response to the application dated October 24, 1994.
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The amendment restructures the primary containment and primary containment leakage technical specifications to reduce the repetition of those requirements contained in NRC regulations such as Appendix J to 10 CFR Part 50. The amendment also supports requested exemptions.
l from Appendix J requirements related to the scheduling of containment j
integrated leak rate te s tr,. In addition to the restructuring and scheduling changes, the amendments incorporates the relocation of the i
list of primary containment isolation valves in accordance with Generic Letter 91-08 and a revision to the interval for functional testing of hydrogen recombiners in ac,cordance with Generic Letter 93-05.
C.
SUBNITTED LICENSEE EVENT REPORTS (Unit 2)
Occurence LER No.
Date Description 95-002 02/03/95 An out of service was placed which affected fire detection zones 2-34 and 35. Per Technical Specification 3.3.7.9, an hourly firewatch must be in affect within one hour of declaring the components out of service. The designated firewatch became offsetive outside of tha allotted time frame. The Operations Department was able to verify that a Radiation Protection technician was in area prior to the designated firewatch becoming effective.95-003 02/21/95 A reactor scram signal was generated as a result of high water level in the south scram discharge volume header while performing a planned refuel outage hydrolazing activity. A high level alarm annunciated and was followed by a scram signal.
The high level' condition in the scram discharge volume cleared after approximately 2 minutes since the vent and drain valves are maintained in a full open position to allow the discharge volume to continually drain during performance of the hydrolazing.95-004 02/23/95 Fire detection zone 2-30 activated when water was introduced into the system from a clean condensate storage system hose break. An hourly fire watch was enacted, but was unable to tour the entire affected zone. The fire marshall was contacted and a proper fire watch for the entire zone was then established.95-005 02/18/95 2B21F028A Outboard Main Steam Isolation Valve failed to close when its control switch was taken to close position.
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D.
DATA TABULATIONS (Unit 2) i 1.
Operating Data Report (See Table 1) l l
2.
Average Daily Unit Power Level (See Table 2) l 3.
Unit shutdowns and significant Power Reductions (See Table 3)
E.
UNIQUE REPORTING REQUIREMENTS (UNIT 2) j 1.
Safety Relief Valve Operations I
(None) 2.
Major Changes to Radioactive Waste Treatment Systems (None) 3.
Static O-Ring Failures l
(None) 4.
Changes to the off-site Dose Calculation Nknual (None) 1 l
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D.1 DPERATING DATA REPORT DOCKET NO. 050-374 TABLE 1 l
UNIT LASALLE TWO DATE April 10,1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 l
OPERATING STATUS 1.
REPORTING PERIOD:
March 1995 GROSS HOURS IN RE?DRTING PERibDe 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 MAX DEPEND CAPACITY (MWe-Net):
1,036 DESIGN ELECTRICAL RATING (MWe-Net):
1,078 l
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POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
4.
REASONS FOR RESTRICTION (IF ANY):
REPORTING PERIOD DATA l
THIS MONTH YEAR TO-DATE CUMULATIVE 5.
REACTOR CRITICAL TIME (HOURS) 0.0 1,152.6 66,360.6 s
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REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.
GENERATOR ON-LINE TIME (HOURS) 0.0 1,152.3 65,137.8 G.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 9.
THERMAL ENERGY GENERATED (MWHt) 0 3,731,007 197,482,935
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 1,281,127 65,969,696
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net)
-8,184 1,230,882 63,415,644
- 12. REACTOR SERVICE FACTOR (%)
0.0 53.4 72.4
- 13. REACTOR AVAILABILITY FACTOR (%)
0.0 53.4 74.3 i
- 14. UNIT SERVICE FACTOR (%)
0.0 53.3 71.1
- 15. UNIT AVAILIBILITY FACTOR (%)
0.0 53.3 71.1 l
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
-1.1 55.0 66.8
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%)
-1.0 52.9 64.2
- 18. UNIT FORCED OUTAGE FACTOR (%)
0.0 0.0 10.4
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURAT!ON OF EACH):
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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1 04/27/95
DOCKET NO. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERACE DAILY UNIT POWER LEVEL (MWe-Net)
DATE April 10,1995 COMPLETED BY M.J. CIALK0WSK!
TELEPHONE (815)-357-6761 REPORT PERIOD:
March 1995 DAY POWER DAY POWER 1
-11 17
-11 2
-11 18
-11 3
-11 19
-11 4
-11 20
-11 5
-11 21
-11 6
-11 22
-11 7
-11 23
-11 8
-11 24
-11 9
-11 25 11 10
-11 26
-11 11
-11 27
-11 12
-11 28
-11 13
-11 29
-11 14
-11 30
-11 15
-11 31
-11 16 11 l
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