NRC-97-0011, Monthly Operating Rept for Dec 1996 for Fermi 2
| ML20133M423 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/31/1996 |
| From: | Giles H, Smith P DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-97-0011, CON-NRC-97-11, RTR-REGGD-01.016, RTR-REGGD-1.016 NUDOCS 9701220385 | |
| Download: ML20133M423 (4) | |
Text
. __
j 4
"{UY).
DeroR r <mi 2 l
Edison EE2:52 gr.t.
l 4
January 15,1997 NRC-97-0011 4
5 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.1996 Enclosed for your information and use is the Fermi 2 Monthly Operating Status Report for December,1996. This report includes the Operating Data Report, Average Daily Unit Power Level, and the Summary of Unit Shutdowns and Power Reductions identified in NRC Regult. tory Guide 1.16 and Fermi 2 Technical Specification 6.9.1.6.
If you have any questions, please contact Harry Giles, at (313) 586-1522.
Sincerely, h $e Vg Peter W. Smitf(
9701220385 961231 Director - Nuclear Licensing PDR ADOCK 05000341 R
PDR Enclosure cc:
A. B. Beach D. R. Hahn 4
M. J. Jordan J
A. J. Kugler
)E N. O'Keefe g
M. V. Yudasz, Jr.
220027
)
Region III
,i p 3
OPERATING DATA REPORT DOCKET NO. 50-341 COMPLETED BY H. B. Giles DATE January 15.1997 TELEPHONE
_{313) 586-1522 OPERATING STATUS 1.
Unit name: Fermi 2 Notes: (1) CalcuNo ising weighted 2.
Reporting period: December.1996 averages to reflect vu nations in rating 3.
Licensed thermal power (MWt): 3430 (MDC and DER).
4.
Nameplate rating (Gross MWe): 1179 Nameplate and DER ratings reflect 98%
5.
Design elect rating (Net MWe): 1116 CTP due to turbine throttle valve 6.
Max dependable cap (Gross MWe): 924 limitations.
7.
Max dependable cap (Net MWe): 876 Scheduled 53 refuel outage extended due to concerns with SRV position indication during surveillance testing.
8.
If changes occur in capacity ratings (Items number 3 through 7) since last report, give reasons:
N/A 9.
Power level to which restricted, if any (MWe Net):
N/A
- 10. Reasons for restriction, if any:
N/A Tills MONTII YEAR TO CUMULATIVE DATE 11.
Hours in reporting period 744 8.784 78.374 12.
Hours reactor was critical 128.3 6.073.1 54.424.7 13.
Reactor reserve shutdown hours 0
Q Q
14.
Hours generator on-line 0
5.859.7 51.496.0 15.
Unit reserve shutdown hours Q
Q Q
16.
Gross thermal energy gen (MWH) 0 18.224.208 157.835.411 17.
Gross elect energy gen (MWH)
Q 5.058.970 50.449.487 18.
Net Elect energy gen (MWH)
Q 4.790.020 48.155.489 19.
Unit service factor Q
66.7 65.7 20.
Unit availability factor 0
66.7 65.7 21.
Unit cap factor (using MDC net)
Q 62.3 59.7 (1) 22.
Unit cap factor (using DER net)
Q 48.9 55.7 (1) 23.
Unit forced outage rate 100.0 22 21.5
- 24. Shutdowns scheduled over next 6 months (Type, Late, Duration of each): None
- 25. If shutdown at end of report period, estimated date of startup: Lanuary 1.1997
- 26. Units in test status (prior to commercial operation): N/A FORECAST ACIIIEVED Initial Criticality N/A N/A Initial Electricity N/A N/A Commercial Operation N/A N/A
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-341 UNIT Fermi 2 DATE January 15.1997 COMPLETED BY H. B. Giles TELEPHONE (313) 586-1522 i
Month December.1996 DAY AVERAGE DAILY DAY AVERAGE DAILY POWER POWER LEVEL LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
i 6
0 22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-341 DATE J_anuary 15.1997 UNIT NAh1E Fermi 2 CONIPLETED BY H. B. Giles l
TELEPHONE G13) 586-1522 REPORT h10 NTH December.1996 i
No. (6)
Date TYPE Dur (Hrs)
Reason (2) hiethod of LER Sys Code (4)
Comp Cause and Corrective Action to (1) shutting down No.
Code Prevent Recurrence j
reactor or (5) l reducing power l
(3) l S96-04 961202 F
98.1 A
2 N/A AC RV Unit shutdown to repair SRV 'A' PS tailpipe pressure switches.
j i
S96-05 961207 F
333.4 A
2 96-022 AC RV Unit shutdown to relocate SRV PS
'A' tailpipe pressure switches.
S96-06 961222 F
27.6 A
2 N/A AC RV Unit shutdown to repair SRV 'D' l
SOL solenoid actuator.
S96-07 961224 F
73.8 A
2 96-023 BF VACB Unit shutdown to repair T23-F400J drywell to torus vacuum breaker.
S96-08 961228 F
82.8 A
3 96-024 JE L1 Reactor scram due to false level 2 j
JC and 8 initiation while vahing in i
reference leg of Rx water level back fill.
(1)
F: Forced (2)
REASON:
(3) hiETHOD:
(4) Instructions for preparation of data entry S: Scheduled A - Equipment Failure (Explain) 1 - hianual sheets for Licensee Event Report (LER) file B - hiaintenance or Test 2 - hianual Scram (NUREG-1022)
C - Refueling 3 - Automatic Scram (5) Same Source as (4)
D - Regulatory Restriction 4 - Continued (6) R - Prefix indicates power reduction.
E - Operations Training and License 5 - Reduced Load S - Prefix indicated plant shutdown.
Examination 9 - Other (7) Duration of reductions reported as zero per F - Administrative Regulatory Guide 1.16, Revision 4.
G - Operational Error (Explain)
H - Other (Explain)
- -