NRC-93-0001, Monthly Operating Rept for Dec 1992 for Fermi 2
| ML20127F716 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/31/1992 |
| From: | Orser W, Stone B DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-93-0001, CON-NRC-93-1 NUDOCS 9301210002 | |
| Download: ML20127F716 (4) | |
Text
.
i.'
William S Orser E necubve Vice President Nxicat Generahon 3;.3 DOITOil-6430 North Dizie H,ghway Nuclear Edison :=r"*
"*8 o"'d* ' '6 o--
' January 15, 1993 NRC-93-0001 U. S. Nuclear Regulatory Commission-Attention: Document Control Desk Washington, D.C.
20555
Reference:
-Fermi 2 NRC Docket No. 50-341 NRC Operating License No. NPF-43
Subject:
Monthly Operating Status Report for December, 1992 Enclosed for your information and use is the Fermi 2 Monthly Operating Status Report for-December, 1992. This report i.
includes the Operating Data Report,: Average Daily Unit Power Level, and-the Summary of Unit Shutdowns and Power Reductions j
identified in NRC Regulatory Guide 1.16 and Fermi 2 Technical l
Specification 6.9.1.6.-
l If you have any questions, please contact Brian Stone, at i
(313) 586-5148.
i l
Sincerely, i
'/ /
t i
i Enclosure-cc:-
T. G. Colburn A. B. Davis j
D. R. Hahn L
W. J. Kropp 1
M. P. Phillips.
P. L. Torpey i
I 1
9 J
4 OPERATING DATA REPORT i
5 DOCKET NO. 50-341 COMPLETED BY B. J. Stone DATE January 15, 1993 TELEP110NE (313) 586-5148
[
OPERATING STATUS j-1.
UNIT NAME:
Fermi 2 l Notes:
(1) Calculated using l
2.
REPORTING PERIOD:
December, 1992 l weighted averages to reflect i
3 LICENSED THERMAL POWER (HWt):
3430 I variations in rating (MDC and l
4.
NAMEPLATE RATING (GROSS MWe):
1179 l DER).
I S.
DESIGN ELECT RATING (Net MUe): 1116 l (2) To be revised following l
6.
MAX DEPENDAULE CAP (GROSS MWe):1110(2)] performance demonstration.
l j
7.
MAX DEPENDABLE CAP (Net MWe):1060 (2) l l
{
8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 Tl! ROUGH 7) SINCE j
LAST REPORT, GIVE REASONS:
9 POWER LEVEL TO Wi!ICH RESTRICTED, IF ANY (MWe Net):
- 10. REASONS FOR RESTRICTION, IF ANY:
THIS MONTil YR TO DATE CUMULATIVE l
- 11. HRS IN REPORTING PERIOD 744 8,784 43,310
- 12. HRS REACTOR WAS CRITICAL 549.8 7,139.5 32,403.2
- 13. REACTOR RESERVE SHUTDOWN liRS 0
0 0
l
- 14. HOURS GENERATOR ON-LINE 534.4 7,020 3 31,047.1
- 15. UNIT RESERVE SHUTDOWN 110VRS 0
0 0
- 16. GROSS THERMAL ENERGY GEN (MWH) 1,614,912__
22,606,104 94,087,295.4 i
- 17. GROSS ELECT ENERGY GEN (MWH) 545,920 7,679,710 31,327,747 j.
- 18. NET ELECT ENERGY GEN (HWH) 523,832 7,356,765 29,949,001
- 19. UNIT SERVICE FACTOR 71.8 79 9 71 7
- 20. UNIT AVAILABILITY FACTOR-71.8 79 9-71 7 f
- 21. UNIT CAP FACTOR (USING HDC NET) 66.4-79.0 64.6 (1) p
- 22. UNIT CAP FACTOR (USING DER NET) 63.1-(1) 76.4 (1)'
-63.2 (1)
- 23. UNIT FORCED OUTAGE RATE O
2.7 7.8
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTilS (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 F
INITIAL ELECTRICITY N/A N/A i
COMMERCIAL OPERATION N/A
-N/A-w W-E Tr
AVERAGE DAILY UNIT POWER LEVEL e
DOCKET NO.
50-341 UNIT FERMI 2 DATE January 15, 1993 COMPLETED BY E. Dawson TELEP110NE (313) 586-5027 Honth December, 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
(HWe-Net) 1 987 17 1117 2
671 18 1121 3
679 19 1118 4
492 20 1123 5
2 21 1124 6
0 22 1121 7
0 23 1119 8
0 24 1125 9
0 25 1071 10 0
26 916 11 0
27 960 12 0
28 957 13 32 29 957 14 1037 30 961 15 1119 31 965 16 1110 l
o UNIT SHUTDOWNS AND POWER REDUCTIONS 0
7 DOCKET NO.
50-341 DATE January 15.
1993 a
UNIT NAME Fermi 2 COMPLETED BV B.
J.
Stone a'ELEPHONE (313) 586-5149 REPORT MONTH December. 1992 i
j METHOD 05 l
4 i
l l
l l
SHUTTING DOWN l LER j SVS l COMP i
CAUSE & CORRECTIVE l
NO.
I DATE TYPE I DuR REASON THE REACTOR NO.
I CODE l CODE ACTION TO PREVENT l
l l (1) l (HRS)'
(2) l OR REDUCING l
(4) f (5)
RECURRENCE l
(6}
l l
(7) l l POWER (3) l l
l I
l I
I I
I i
i i
i R 92-03 12/02/92 I F
0 l
A l
5 l
N/A l SE lEXJ/PSPl Recirculation rsnoac> on loss of i
l l
l 1 Heater Drains.
I I
I i
i i
R 92-04 12/04/92 S
O B
1 1
N/A l SE lExJ/PSpl Power reduction to monitor #4 l
l l
]
}
} Feec=ater Heater Estraction Steam j
l 1
1 l
l 1
l Line, I
f 1
i i
i I
l S 92-05 i 12/05/92 1 5 1209.6 l A
l 1
N/A l SE lEAJ/PSPI Repair o*
entraction steam time i
i t
I i
I i
I rupture.
I I
f I
l I
(1) F:' FORCED (2) REASON:
(3) METHOD:
(4) INSTRUCTIONS FOR S: SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM ENTRY SNEETS FOR LICENSEE C - REFUELING 3-AUTOMATIC SCRAM EVENT REPORT (LER) FILE D - REGULATORY RESTRICTION 4 - CONTINUED (NUREG-1022)
E - OPERATOR TRAINING & LICENSE EXAMINATION 5 - REDUCED LOAD F - ADMINISTRATIVE 4 - OTHER G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER (EXPLAIN)
(5) SAME SOURCE AS (4)
(6) R - PREFIA INDICATES POWER REDUCTION.
5-PREFIA INDICATES PLANT SHUTDOWN.
(7) DURATION Oc REDUCTIONS REPORTED AS 2ERO PER REG.
GUIDE 1.16 REv. 4 i