ML20077A672
ML20077A672 | |
Person / Time | |
---|---|
Site: | Limerick |
Issue date: | 10/31/1994 |
From: | Kelley S, Muntz J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9411250127 | |
Download: ML20077A672 (11) | |
Text
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YT-8.imerick Generatirg Ct tlin
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P O ENRGY reco e erav ce-ae"r PO Box 2300 i Sanatoga, PA 19464-0920 .. l i
t T.S.6.9.1.6 November 14, 1994 Docket Nos 50-352 I 50-353 License Nos. NPF-39 [
NPF-85 j U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 t
Subject:
Limerick Generating Station Monthly Operating Report i For Units 1 and 2 -
Enclosed are the monthly operating reports for Limerick Units 1 [
and 2'for the month of October 1994 forwarded pursuant to l Technical Specification 6.9.1.6. ;
Very truly yours, ,
, , f' $M James A. Muntz !
Director - Site Engineering ,
sjk Enclosures ,
T. T. Martin, Administrator, Region I, USNRC (w/ enclosures) cc:
N. S. Perry, USNRC Senior Resident Inspector LGS (w/ enclosures)
D. R. Helwig, Vice President, Limerick Generating Station 20000 9411250127 DR 941033 $
'"(kh ADOCK 05000352 )
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Docket No. 50-352 '
< Attachment to Monthly
-t Operating Report for October 1994 Limerick Generating Station ;
Unit 1 October 1 through October 31, 1994 ,
I. ' Narrative Summary of Operating Experiences i
Unit 1 began'the month of October at a nominal 100% of rated '
thermal power (RTP).
On October 7, 1994, at 1901 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.233305e-4 months <br />, a power reduction was started for planned maintenance work on the Steam Jet Air Ejector after condenser cooler. The main turbine was i removed from service, due to high vibration at the number 3 bearing, at 0432 hours0.005 days <br />0.12 hours <br />7.142857e-4 weeks <br />1.64376e-4 months <br /> on October 8, 1994. At 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br /> power was reduced to 8% RTP. Maintenance work was successfully completed and at 1631 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.205955e-4 months <br /> on October 8, 1994, -
the output breaker was closed and power ascension began.
On October 8, 1994, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, a generator stator water coolant runback occurred from 50.7% RTP. Power was ,
stabilized at 39% RTP. The cause of this event was insufficier.c cooling flow to the stator water coolant system. '2his condition was corrected and oower increase '
commenced shortly.thereafter.
On October 10, 1994, at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />. power was reduced to 65.2% RTP for a control rod pattern adjustment. Power was returned to 100% RTP at 2112 hours0.0244 days <br />0.587 hours <br />0.00349 weeks <br />8.03616e-4 months <br />.
On October 23, 1994, at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, power was reduced to [
58.4% RTP in order to perform flux tilt testing This '
testing continued until October 25, 1994, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />.
Power ascension began at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on October 25, 1994. l Power was restored to 100% RTP on October 27, 1994. j Unit 1 ended this operating period at 100% of RTP. !
II. Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relicf Valves during the month of October.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 352 UNIT LIMERICK UNIT 1 DATE NOVEMBER 14,1994 /
COMPANY PECO ENERGY COMPANY STEVEN J. MELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3763 MONTH OCTOBER 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 1053 17 1059 2 1055 18 1057 3 1058 19 1053 4 1058 20 1038 5 1060 21 1044 6 1057 22 1053 7 958 23 624 8 103 24 578 9 918 25 663 10 1014 26 930 11 1060 27 1029 52 1062 28 1057 13 1058 29 1044 14 1055 30 1106 15 1059 31 1044 16 1058
_. m.____-..--_, . - - - . , _ _ . - . . . - _ . _ . . . . - -- --- me, . - - - - , - - - - - - - . - - - - - - , ---- .- . -- --- - - - - - -
OPERATING DATA REPORT a
DOCKET NO. 50 - 352 -
DATE NOVEMBER 14.1994 COMPLETED BY PECO ENERGV COMPANY /
STEVEN J. KELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3763 OPERATING STATUS
- 1. UNIT NAME: LIMERICK UNIT 1 NOTES: THERE WERE THREE LOAD DROPS 2, REPORTING PERIOD: OCTOBER. 1994 GREATER THAN 20% THIS MONTH
- 3. LICEMSED THERMAL POWER (MWT): 3293 DUE TO HIGH TUPPINE VIBRATION.
4 NAMEPLATE RATING (GROSS MWE): 1138 A STATOR WATER COOLING PROBLEM
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1055 AND FOR FLUX TILT TESTING.
- 6. MAXIuuM DEPENDABLE CAPACITY (GROSS MWE): 1092
- 7. MAXIWUM DEPENDABLE CAPACITV (NET MWE): 1055
- 8. IF CHANGES OCCUR IN CADACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS. IF ANY:
THIS MONTH YR-TO-DATE CUMOLATIVE 11 HOURS IN REPORTING PERIOD 745 7.296 76.680
.-- - ------------ -------~~ --
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 745.0 6.445.2 62.644.3
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 733.0 6.376.7 61.561.5 l 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 2.265.583 20.059.409 189.510.168 17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 747.580 6.552.130 61.594.170
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 721.517 6.321.544 59.107.534 PAGE 1 OF 2 i
- _ _ , ___ ' ________________M
l OPERATING DATA REPORT (CONTINUED) DOCMET NO. 50 - 352 I
I s
I DATE NOVEMBER 14.1994 i
THIS MONTH YR-TO-DATE CUMULATIVE-l 19. UNIT SERVICE FACTOR 98.4 87.4 80.3
- 20. UNIT AVAILABILITY FACTOR 98.4 87.4 80.3
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 91.8 82.1 73.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 91.8 82.1 73.1
- 23. UNIT FORCED OUTAGE RATE 1.6 1.1 4.4 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUD:
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITV 12/19/84 12/22/84 INITIAL ELECTRICITV MID APRIL 85 4/13/85 COMMERCIAL OPERATION IST QTR 86 2/01/86 PAGE 2 OF 2
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 352 UNIT NAME LIMERICK UNIT 1 DATE NOVEMBER 14.1994
- REPORT MONTH OCTOBER. 1994 COMPLETED BY PECO ENERGY COMPANY STEVEN J. KELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3763 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT * (4) (5) l PREVENT RECURRENCE 33 941000 F 000.0 A 4 N/A HA TURBIN REACTOR POWER WAS REDUCED TO 8%
DUE TO HIGH TURBINE VIBRATION.
34 941008 F 000,0 A 4 N/A AD GENERA REACTOR POWER WAS REDUCED TO 39%
DUE TO STATOR WATER COOLING.
35 941010 S 000.0 B 4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 85.2% FOR A CONTROL ROD PATTERN ADJUSTMENT.
36 941019 5 000.0 B 4 N/A RB VESSEL REACTOR POWER WAS REDUCED TO 58.4%
FOR FLUX TILT TESTING.
(1) (2) (3) (4)
F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161) i E - OPERATOR TRAINING + LICENSE EXAMINATION l F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN) l H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE i
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Docket No. 50-353 Attachment to Monthly Operating Report for October 1994 Limerick Generating Station Unit 2 October 1 through October 31, 1994 I. Narrative Summary of Operating Experiences Unit 2 began the month of October at a nominal 100% of Rated Thermal Power (RTP). Power reduction occurred throughout the month due to end-of-cycle coastdown.
On October 9, 1994, at 1828 hours0.0212 days <br />0.508 hours <br />0.00302 weeks <br />6.95554e-4 months <br />, power was reduced to 95%
RTP due to a 'B' feedwater heater string isolation. Power was restored to 99.8% RTP by 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
On October 14, 1994, at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> the '5C' feedwater heater was removed from service resulting in a power increase from 92.8% RTP to 95.3% RTP.
On October 16, 1994, at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br />, power was reduced to 91.8% RTP for main turbine valve testing. Power was restored to 94%'RTP at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br />.
On October 19, 1994, at 1218 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.63449e-4 months <br />, a full reactor Scram signal was received due to low reactor water level. The cause of this event was a relay coil failure combined with an inappropriate action by a reactor operator during the performance of the 'D24' monthly diesel generator surveillance test. The unit remained in Operation condition 3, Hot Shutdown, until October 20, 1994, at 0402 hours0.00465 days <br />0.112 hours <br />6.646825e-4 weeks <br />1.52961e-4 months <br />, when the mode switch was taken to Operational Condition 2, Startup. At 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br /> power increase commenced and at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br />, on October 21, 1994, the reactor was critical. The main generator was synchronized to the grid at 1501 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.711305e-4 months <br />.
Power was increased to 92% RTP by 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> on October 23, 1994.
Unit 2 ended this operating period at 88.8% of RTP in end-of-cycle coastdown.
II. Challenges to Main Steam Safety Relief Valves There were no. challenges to the Main Steam Safety Relief Valves during the month of October.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 353 ,
UNIT LIMERICK UNIT 2 DATE NOVEMBER 14.1994 .
COMPANY PECO ENERGY COMDANY STEVEN J. MELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3763 MONTH OCTOBER 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 1034 17 948 2 1037 18 940 3 1025 19 475 4 1023 20 0 5 1021 21 48 6 1013 22 415 7 1008 23 573 8 983 24 925 9 987 25 929 10 955 26 932 11 968 27 932 12 961 28 928 13 954 29 909 14 956 30 957 15 964 31 896 16 952 I
4 OPERATING DATA REPORT DOCKET NO. 50 - 353 ,'
DATE NOVEMBER 14.1994 CCMPLETED BY PECO ENERGY COMPANY .
STEVEN J. KELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3763 OPERATING STATUS 1 UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WAS ONE LOAD DROP
- 2. REPORTING PERIOD: OCTOBER, 1994 GREATER THAN 20% THIS
- 3. LICENSED THERMAL POWER (MWT): 3293 MONTH DUE A SCRAM CAUSED BY 4 NAMEPLATE RATING (GROSS WWE): 1138 A RELAY COIL FAILURE COMBINED &
- 5. DESIGN ELECTRICAL RATING (NET MwE): 1055 WITH AN INAPPROPRIATE ACTION
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1092 BY AN OPERATOR DURING A TEST
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1055 ON A DIESEL GENERATOR.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS. IF ANY:
THIS MONTH VR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 745 7.296 42.192
. --... --------~~-- --------.. .
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 705.4 7.256.4 37.899.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 694.3 7.194.2 37.140.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 2.069.256 23.320.868 118.625.949
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 665.020 7.747.580 39.240.106
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 639.343 7.477.802 37.808.494 PAGE 1 OF 2
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OPERATING DATA REPORT (CONTINUED) DOCMET NO. 50 - 353 DATE NOVEMBER 14.1994 THIS MONTH VR-TO-DATE CUMULATIVE
- 19. UNIT SERVICE FACTOR 93.2 98.6 88.0
- 20. UNIT AVAILABILITY FACTOR 93.2 98.6 88.0 21 UNIT CAPACITY FACTOR (USING MDC NET) 81.3 97.1 84.9
. -------u---- -------...--
- 22. UNIT CAPACITY FACTOR (USING OER NET) 81.3 9T.1 84.9
- 23. UNIT FORCED OUTAGE RATE 6.8 1.4 3.6 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
REFUELING OUTAGE IS SCHEDULED FOR 1/28/95: DURATION OF 32 DAYS
- 25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89 09/01/89 COMMERCIAL OPERATION 02/01/90 01/08/90 I
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. UNIT SHUTDOWNS QND POWER REDUCTIONS DOCCET NO. 50 - 353 UNIT NAME LIMERICK UNIT 2 DATE NOVEMBER 14,1994 REPORT MONTH OCTOBER, 1994 COMPLETED BY PECO ENERGY COMPANY .
STEVEN J. KELLEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) T18-3763 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE- DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO. DATE (1) (HOURS)l (2) REACTOR (3) REPORT * (4) (5) i PREVENT RECURRENCE 23 941009 5 000.0 H 4 N/A CH INSTRU REACTOR POWER WAS REDUCED TO 95% FOR END OF CYCLE COASTDOWN.
24 941016 5 000,0 B 4 N/A HA INSTRU REACTOR POWER WAS REDUCED TO 91.8% FOR MAIN TURBINE VALVE TESTING.
25 941019 F 039.6 A 3 2-94-10 CH INSTRO REACTOR SCRAM ASSOCIATED WITH A RELAY COIL FAILURE COMBINED WITH AN IN-APPROPRIATE ACTION TAKEN BY AN OPERATOR DURING TESTING OF AN EMERGENCY DIESEL GENERATOR.
39.6 (1) (2) (3) (4)
F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS i S- SCHEDULED A - EOUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)
D- REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161)
E - OPERATOR TPAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H- OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE
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