NRC-93-0054, Monthly Operating Rept for Apr 1993 for Fermi 2
| ML20036B271 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/30/1993 |
| From: | Gipson D, Stone B DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-93-0054, CON-NRC-93-54 NUDOCS 9305180430 | |
| Download: ML20036B271 (4) | |
Text
T s
Douglas R. Gipson vice Presdent Nucicar Operatons Detroi,.t r-m unn o. v.n
- CISOn awraTr -
E"#'La.
May 15, 1993 NRC-93-0054 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555
Reference:
Fermi 2 t
NRC Docket No. 50-341
^
NRC Opereting License No. NPF-43
Subject:
Monthly Operating Status Report for April, 1993 I
Enclosed for your information and use is the Fermi 2 Monthly Operating Status Report for April, 1993 This report includes the Operating Data Report, Average Daily Unit Power Level, and l
the Summary of Unit Shutdowns and Power Reductions 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 I
(313) 586-5148.
Sincerely, W
5 Enclosure cc:
T. G. Colburn D. R. Hahn W. J. Kropp J. B. Martin M. P. Phillips P. L. Torpey l
t
}00bb 9305180430 930430 l]
PDR ADOCK 05000341 I
R pop
4 OPERATING DATA REPORT DOCKET NO.
50-341 COMPLETED BY
,B. J. Stone DATE
_May 15, 1993 TELEPHONE (313) 586-5148 OPERATING STATUS 1.
UNIT NAME:
Fermi 2 l Notes:
(1) Calculated using weight-l 2.
REPORTING PERIOD: April, 1993 I ed averages to reflect variations l
3 LICENSED THERMAL POWER (MWt): 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 MWe): 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 l pressure limit; all ratings reflect l I this power level.
l 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
N/A I
9 POWER LEVEL TO WHICH RESTRICTED, IF ANY (MWe Net):
(2)
- 10. REASONS FOR RESTRICTION, IF ANY:
(2)
THIS MONTH YR TO DATE CUMULATIVE
- 11. HRS IN REPORTING PERIOD 719 2,879 46,189
- 12. HRS REACTOR WAS CRITICAL 465.1 2,529.6 34,932.8
- 13. REACTOR RESERVE SHUTDOWN HRS 0
0 0
- 14. HOURS GENERATOR ON-LINE 446.0 2,492.5 33,539.6
- 15. UNIT RESERVE SHUTDOWN HOURS 0
0 0
- 16. GROSS THERMAL ENERGY GEN (MWH) 1,368,960 8,052,144 102,139.439.4
- 17. GROSS ELECT ENERGY GEN (MWH) 453,630 2,756,970 34,084,717
- 18. NET ELECT ENERGY GEN (MWH) 434,551 2,649,891 32,598,892
- 19. UNIT SERVICE FACTOR 62.0 86.6 72.6
- 20. UNIT AVAILABILITY FACTOR 62.0 86.6 72.6
- 22. UNIT CAP FACTOR (USING DER NET) 54.2 (1) 82.5 (1) 64.5 (1)
- 23. UNIT FORCED OUTAGE RATE 7.0 5.6 7.6
- 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 i
COMMERCIAL OPERATION
_ N/A N/A
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-341 UNIT FERMI 2 DATE May 15, 1993 f
COHPLETED BY E. Dawson TELEPHONE (313) 586-5027 I
Month April, 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1110 17 0
2 1116 18 0
i 3
1112 19 0
4 1116 20 0
5 1112 21 0
6 1111 22 389 7
1008 23 997 8
776 24 1035 9
661 25 1039 10 451 26 1052 i
11 0
27 1053 12 0
28 1041 13 0
29 1037
?
14 0
30 1036 i
15 0
31 N/A 16 0
i I
i i'
UNIT $HUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-341 DATE May 15. 1993 UNIT NAME Fermi 2 COMPLETED BY B.
J.
Stone TELEPHONE (313) 586-5140 REPORT MONTH April, 1993
}
l l
l l
} METHOD OF 1
l 4
l l
l l
l l SHUTTING DOWN l LER I 5YS COMP CAUSE & CORRECTIVE l
NO.
DATE I TYPE l DUR l REASON i THE REACTOR NO.
l CODE CODE ACTION TO PREVENT l
l (1)
I (HRS)l (2)
OR REDUCING l
(4)
(5)
RECURRENCE l
(6) 1 (7) l POWER (3) i I
R 93-01 04/06/93 F
0 A
5 N/A 5E EXJ/ PSP Power reduct.on to monitor s4 Feedwater Hester Extraction Steam l
Line.
I 5 93-03a 04/10/93 5
239.6 A
1 l N/A SE EXJ/ PSP Repair of entraction steam line l
rupture.
I 5 93-03b 04/20/93 F
33.4 H
3 193-007 N/A N/A Screw occurred during recovery from entraction steam line repair outage (i.e..
failed startup).
I Scram caused by incorrectly installed test instrument which l
1eaked steam and water onto Main l
l Steam manifold pressure trans-l l
mitters.
The transmitters' failure initiated reactor pressure and I
feedwater transient. causing l
l reactor to trip from IRM's upscale.
I I
I (1) F: FORCED (2) REASON:
(3) LETHOD (4) INSTRUCTIONS FOR 5: SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL PREPARATION Ok DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM ENTRY SHEET 5 FOR LICENSEE C - REFUELING 3-AUTOMATIC SCRAM EVENT REPORT (LER) FILE D - REGULATORY RESTRICTION 4 - CONTINUED (NUREG-1022)
E - OPCRATOR TRAINING & LICENSE EXAMINATION 5-REDUCED LOAD F - ADMINISTRATIVE 9 - OTHER G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER (EXPLAIN)
(5) SAME'5OURCE A5 (4)
(6) R - PREFIX INDICATES POWER REDUCTION.
5 - PREFIX INDICATES PLANT SHUTDOWN.
(7) DURATION OF REDUCTIONS REPORTED A5 ZERO PER REG.
GUIDE 1.16 REV. 4
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