ML20206R950
| ML20206R950 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1998 |
| From: | Lin S, Venable J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-99-00003, GNRO-99-3, NUDOCS 9901270006 | |
| Download: ML20206R950 (5) | |
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..w' EntIrgy Operstions, Inc.
V-h P. O. Box 756 Port Gibson. MS 39150 Toi 601437 2129
.a Joseph E. Venable Ge< mal Manager Plant Operabors Grand Gulf Nuclear Stapon January 14, 1999 i
U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 l
Attention:
Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 l
Monthly Operating Report GNRO-99/00003 Gentlemen:
In accordance with the requirement of Technical Specification 5.6.4, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for December 1998.
If you have any questions or require additional information, please contact this office.
7 Yours truly,
/
e JEV/SDUcg attachments: 1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions cc:
(See Next Page)
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4 9901270006 981231 I PDR ADOCK 05000416 R
PML i
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_. _ _ ~. _. _. _ _.. _.. _ _ _.
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.j GNRO-99/00003
. Page 2 of 3 1
cc:
Mr. N. S. Reynolds (w/a) l Mr. Jager Smith (w/a)
Mr. H. L. Thomas (w/o)
Ms. K. D. Weaver (w/a)
- i Mr. J. W. Yelverton (w/a)
Mr. Ellis W. Mershoff (w/a)
Regional Administrator-
- U.S. Nuclear Regulatory Commission -
Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 Mr. Jack Donohew, Project Manager i
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 i
6 t
. to GNRO-99/00003 DOCKET NO 50-416 DATE O1/08/99 COMPLETED BY S. D. Lin l
TELEPHONE (601) 437-6793 MONTH:
D-:- -s 1998 1-l-
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
I 1262 17 1280
-2 1260
'I8 1277 l
3 1257 19 1250 4
1250 20 1258 5
1230 21 1251 6
1247 22 1287 7
1248 23 1289 8
1268 24 1289 9
1266 25 1290 10 1277 26 1288 11 1276 27 1277 12 1277 28 1277 13 1279 29 1279 14 1279 30 1285 15-1222 31 1280 16 1280
l
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Attachment I to GNRO-99/00003 l
DOCKET NO
$0-416 DATE 01/08/99 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 OPERATING STATUS 1.
Unit Name: GGNS UNIT 1 2.
Reportag Period: December 1998 3.
Licensed Thermal Power (MWt): 3833 MWT I
4.
Nameplate Rating (Gross MWe): 1372.5 MWE
- 5. - Design Electrical Rating (Net MWe): 1250 MWE 6.
Maximum Dependable Capacity (Gross MWe): 1254 MWE 7.
. Maximum Dependable Capacity (Net MWe):
1204 MWE 8.
If changes occur in Capacity Ratings (Items 3 through 7) Since Last Report. - Give Reason:_
9.
Power level To Which Restricted, if Any (Net MWe): N/A
- 10. Reasons For Restrictions, if Any:
N/A This Month Yr to Date Cumulative *
- 11. Hours in Reporting Period 744 8,760 124,480
- 12. Number of Hours Reactor was Critical 744.0 7,784.5 104,523.5
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 744.0 7,642.3 101,279.2
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2,848,049 28,439,272 364,849,567
- 17. Gross Electrical Energy Generated (MWH) 981,848 9,562,322 118,081.122 18.' Net Electrical Energy Generated (MWH) 945,584 9,190.811 113.232,720
- 19. Unit Service Factor '
100.0 87.2 83.0
- 20. Unit Availability Factor 100.0 87.2 83.0
- 21. Unit Capacity Factor (Using MDC Net) 105.6 87.3 81.8
- 22. Unit Capacity Factor (Using DER Net) 101.7 83.9 75.3
- 23. Unit Forced Outage Rate 0.
3.2 5.5
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None
- 25.. If Shut Down At End of Report Period. Estimated Date of Startup: N/A
- 26. - Units in Test Status (Prior to Commercial Operation):
l Forecast Achieved INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 l
COMMERCIAL OPERATION 07/01/85 l
- Items 11 thwgh 18 are cumulative results since initial electricity i'
ea 4
Attaciuneet 3 to GNRO-99.00003 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONYH D C L.1998 No.
Date '
Type (1)
Duration Reason Method Of Licensee Event System Code Component Cause & Corrective Action To Prevent Hours (2)
Shutting Down Report #
(4)
Code (5)
Recumace (CACA)
Reactor (3)
None 1
2 3
4 5
F: Forced Reason:
Method:
Exhibit G - Instructions for Preparation of Exhibit 1 - Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets for Licensee Event
. B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator Training &
5-Reduced load Licensing Examination 6-Other F-Administrative G-Operational Error (Explain)
H-Other (Explain)
- -