ML20128K400
| ML20128K400 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/31/1993 |
| From: | Cottle W, Daughtery L ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-93-00017, GNRO-93-17, NUDOCS 9302180159 | |
| Download: ML20128K400 (5) | |
Text
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I Entergy Operations,inc.
g c-=',ENTERGY m aam nac.natus m m Jr W1437 6403 l
February 11, 1993
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1, m L'g:f t)(L.2 ? Lt if t.iG U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.
20555 Attention:
Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1
-Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-93/00017 Gentlemen:
In accordance with the requirement of Technical.. Specification 6.9.1.10, Entergy Operations is providing the Monthly Operating Report for Grand Gulf-Nuclear Station Unit 1 for January 1993..
If you have any questions or require additional information, ploase contact this office.
Yours-truly, wi W
WTC/'A'MC/cg attachments:
1.
Operating Status
'2.
Average Daily Power Level 3.-
. Unit Shutdowns and Power Reduction.
cc:
(See Next Page) 18f.100
- 1 9302180159 930131-
.../
PDR ADOCK 05000416 I
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v February 11, 1993 GNRO-93/00017 Page 2 of 3 cc:
Mr. R. H. Bernhard (w/a)
Mr.
D.
C. Hintz (w/a)
Mr..R. B. McGehee (w/a)-
Mr. N.
S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator j
U.S. Nuclear Regulatory Commission Region II 101 Marietta St.,
N.W.,
Suite 2900 Atlanta, Georgia 30323 Mr. P.
W.
O'Connor, Project-Manager (w/2)
Office of Nuclear Reactor Regulation U.S.
Niclear Regulatory Commission Mall _Stop 13H3 Washington, D.C.
20555 a
b I
~~
7
-- to GNRO-93/00017 p,,
DOCKET NO.
_50-416 DATE 02/03/93 COMPLETED BY L.
F.
Daughtery_.
TELEPHONE
_(601) 427-2334 OPERATING STATUS 1.
Unit Name:
GGNS UNIT 1 2.
Reporting Period:
January 1993 3.
Licensed Thermal Power (MWt):
3833 MWT 4.
Nameplate Rating (Gross MWe):
1372.5 MWE 5.
Design Electrical Rating (Net MWe):
1250 MWE 6.
Maximum Dependable Capacity (Gross MWe): _1190 MWE 7.
Maximum Dependable Capacity (Net MWe):
1143 MWE 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 (Net NWe):
N/A 10.
Reasons For Restrictions, If Any:
N/A This Month yr to Date Cumulative 11.
Hours In Reporting Period 744.0 744.0 72,640 12.
Number of Hours Reactor Was Critical 744.0 744.0 58,290.1 13.
Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 744.0 744.0 55.957.7 15.
Unit Reserve Shutdown Hours 0 _
0 0
16.
Gross Thermal Energy Generated (MWH) 2.816,954 2,816,954 195,057,094 17.
Gross Electrical Energy Generated (MWH) 923,215 923,285 62,005,117 18.
Net Electrical Energy Generated (MWH) 888.229-888,222 59,320,092 19.
Unit Servico Factor 100.0 100.0 79.5' 20.
Unit Availability Factor 100.0 100.0 79.5 21.
Unit Capacity Factor (Using MDC Net) 104.5 104.5 76.2 22.
Unit Capacity Factor (Using DER Net) 95.5 95.5 69.1 23.
Unit Forced Outage Rate 0
0 6.2 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date and 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).
4 Forecast Ag]L wy_ej;l e
INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85 l
l i
ll, to GNRO-93/00017 DOCKET NO.
50-416 UNI?'
1 DATE 02/03/93 COMPLETED 3Y L.
F.
Daughterv TELEPHONE (601) 437-2334 MONTH January 1993 j
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Nat)
(MWe-Net) i1 1215 17 1209 2
1207 18 1202 3
1192 19 1211 1
- 4 1188 20 1190 5
1213 21 1206
- 6 1213 22 1202 I7 1210 23 984 8
121.Q 24 1186 9
1199 25 1216 10 1209 26 1216 11 1213 27 1213 12 1207 28 1210 I 13 1212 29 1211 14 1013 30 1214
- 15 1212 31 1213 s
- 16 1210 N/A f
k
o s to GNRO-93/00017 UNIT SHUTDOWNS AND POWER REDUCTIONS
~
DOCKET NO.
50-416 UNIT 1
DATE 02/03/93 COMPLETED BY L.
F. DAUGHTERY TELEPHONE (601) 437-2334 REPORT MONTH January 1993 No.
Date Type Duratien Reason Method of Licensee System Component Cause &
(1)
Hours (2)
Shutting Event Code Code Corrective Down Report #
(4)
(5)
Action to Reactor Prevent (3)
Recurrence (C&CA) 93-01/14/93 S
16.9 B
5 N/A N/A N/A Rx thermal power reduction to 001 approximately 65%
for repairing steam leaks.
93-01/23/93 S
20.3 B
5 N/A N/A N/A Rx thermal power reduction to 002 approximately 65%
for control rod sequence exchange.
UNIT SHUTDOWNS AND POWER REDUCTIONS 1
2 3
4 F:
Forced Reason:
Method:
Exhibit G - Instructions S:
Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)
C-Refueling 4-Continued File (NUREG-Ol61)
D-Regulatory Restriction 5-Reduced load E-Operator Training &
6-Other License Examination F-Administrative G-Operational Error 5
(Explain)
Exhibit 1 - Same Source H-Other (Explain)
.