NRC-93-0025, Monthly Operating Rept for Feb 1993 for Fermi 2
| ML20034H368 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/28/1993 |
| From: | Dawson E, Orser W, Stone B DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-93-0025, CON-NRC-93-25 NUDOCS 9303170246 | |
| Download: ML20034H368 (4) | |
Text
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Wa!!iam S. orser Execut:ve Ve:e Presiderit Nacasas oeneratton fyQ
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6400 North Dmic H; Edison ram"ghway Nuclear o--
Reg Guide 1.16 March 15, 1993 NRC-93-0025 l
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555
Reference:
Fermi 2 NRC Docket No. 50-341 l
NRC Operating License No. NPF-43 i
Subject:
Monthly Operating St.atus Report for February, j
1993 i
Enclosed for your information and use is the Fermi 2 Monthly l
Operating Status Report for February, 1993 This report l
includes the Operating Data Report, Average Daily Unit Power l
Level, and the Summary of Unit Shutdowns and Power Reductions I
identified in NRC Regulatory Guide 1.16 and Fermi 2 Technical Specification 6.9.1.6.
If you have any questions, please contact Brian Stone, at (313) 586-5148.
Sincerely, L
Enclosure l
cc:
T. G. Colburn A. B. Davis D. R. Hahn W. J. Kropp M. P. Phillips P. L. Torpey 9303170246 930228 PDR ^ADOCK 05000341 Mk R
PDR I
- &e r
OPERATING DATA REPORT DOCKET NO. 50-341 COMPLETED BY B. J. Stone DATE March 15, 1993 TELEPHONE (313) 586-5148 OPERATING STATUS 1.
UNIT NAME:
Fermi 2 l Notes:
(1) Calculated using weight-l 2.
REPORTING PERIOD: February, 1993 i ed averages to reflect variations i
3 LICENSED THERMAL POWER (MWL):
3430 l in rating (MDC and DER).
l 4.
NAMEPLATE RATING (GROSS MWe):
1179 l (2) Currently operating at 98% CTP l
5.
DESIGN ELECT RATING (Net MWo): 1116 l maximum due to throttle valve l
6.
MAX DEPENDABLE CAP (GROSS MWe):1135 l limitations at the current operating l 7
MAX DEPENDABLE CAP (Net MWe):1085 I pressure limit; all ratings reflect l l this power level.
l 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE 3
LAST REPORT, GIVE REASONS:
N/A 9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (MWe Net):
(2)
- 10. REASONS FOR RESTRICTION, IF ANY:
(2) l THIS MONTH YR TO DATE CUMULATIVE
- 11. HRS IN REPORTING PERIOD 672 1,416 44,726
- 12. HRS REACTOR WAS CRITICAL 576.5 1,320.5 33,723.7
- 13. REACTOR RESERVE SHUTDOWN HRS 0
0 0
- 14. HOURS GENERATOR ON-LINE 558.5 1,302.5 32,349.6
- 15. UNIT RESERVE SHUTDOWN HOURS 0
0 0
- 16. GROSS THERMAL ENERGY GEN (MWH) 1,798,680 4,191,792 98,279,084.4
- 17. GROSS ELECT ENERGY GEN (MWH) 619,850 1,445,710 32,773,457
- 18. NET ELECT ENERGY GEN (MWH) 595.519 1,389,972 31,338,973
- 19. UNIT SERVICE FACTOR 83.1 92.0 72.3
- 20. UNIT AVAILABILITY FACTOR 83.1 92.0 72.3
- 22. UNIT CAP FACTOR (USING DER NET) 79.4 (1) 88.0 (1) 64.0 (1)
- 23. UNIT FORCED OUTAGE RATE 16.9 8.0 7.8
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION OF EACH):
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
[.
~
L I-AVERACE DAILY UNIT POWER LEVEL J-DOCKET NO.
50-341 UNIT FERMI 2 DATE March 15. 1993' COMPLETED BY E. Dawson TELEP110NE (313) 586-5027 Honth February, 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t.)
(MWe-Net) 1 1124 17 1125 2
1126 18 1122 3
1118 19 1125 4
1120 20 0
5 1115 21 777 6
1070 22 1118 7
1122 23 1121 8
1122 24 1123 9
1055 25 1124 10 131 26 1122 11 0
27 1124 12 0
28 1122 13 29 29 N/A 14 898 30 N/A
- 15 1121 31 N/A 16 1121 4
t 4
UNIT SHUTDOWNS AND POWER REDUCTIONS
'ei DOCKET NO.
50-341 DATE March 15. 1993 4
UNIT NAME Fermi 2 COVPLETED BY B.
J.
Stone TELEPHONE (313) 586-5148 REPORT MONTH February. 1993 METHOD OF SHUTTING DOWN LER SYS COMP CAUSE & CORRECTIVE NO.
DATE TYPE DUR REASON THE REACTOR NO.
CODE CODE ACTION TO PREVENT (1)
(HRS)
(2)
OR REDUCING (4)
(5)
RECURRENCE (6)
(7)
POWER (3)
$ 93-01 02/10/93 F
81.8 B
1 N/A SG
- Cond Condenser tube leak caused condensate chemistry to reach action levels plant shutdown for tube plugging.
S 93-02 02/19/93 F
31.7 G
3 93-004
- KE
- 27 &
Routine pump breaker PM testing 94 inadvertently actuated in-service trip relays an in-service pump breaker trip relay failed to Drcoerly actuate. leading to inability to' transfer feed to.
alternate supply..The loss of power to two (2) circulating water cumps and their associated dis-charge valves resulted in in-adequate cooling water flow to the condenser leading to turbine tr9p on high concenser backpressure.
(1)
F*
~ >ED (2) REASON.
(3) METHOD:
(4) INSTRUCTIONS FOR
~
+.DULED A - EOUIPMENT FAILURE (EXPLAIN) 1 - MANUAL DREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM EVENT REPORT (LER). FILE D - 6:EGULATORY RESTRICTION 4 - CONTINUED (NUREG-1022)
E - OPERATOR TRAINING & LICENSE EXAMINATION 5 - REDUCED LOAD F - ADMINISTRATIVE 9 - OTHER G - O?ERATIONAL ERROR (EXPLAIN)
H - OTHER (EXPLAIN)
(5) SAME SOURCE AS (4)
~*
- SG = CONDENSEP SYSTEM: COND w CONDENSER (6) R - PREFIX INDICATES POWER KE e HEAT REJECTION SYSTEMt 27 = RELAY. UNDERVOLTAGE: 94 = RELAY. TRIPPING REDUCTION.
5 - PREFIX INDICATES PLANT SHUTDOWN.
(7) DURATION OF REDUCTIONS REPORTED AS ZERO PER REG.
GUIDE 1.16 REY. 4 s
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