ML20133M111
| ML20133M111 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1996 |
| From: | Hagan J, Lin S ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-97-00005, GNRO-97-5, NUDOCS 9701220265 | |
| Download: ML20133M111 (5) | |
Text
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Entergy Operadons,Inc.
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I PO. Box 756
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Port Gibson. MS 39150
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Tel 601437 6408 Fax 601437 2705 i
Joseph J. Hagan e
i
%ce Prr:sident l
Opo<at:ons January 15, 1997 orand cuit nuaear staiion l
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1 i
U.S. Nuclear Regulatory Commission l
Mall 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-97/00005 l
l Gentlemen:
In accordance with the requirement of Technical Specification 5.6.4, Entergy Operations is providing the l
Monthly Operating Report for Grand Gulf Nuclear Station Unit i for December 1996.
If you have any questions or require additionalinformation, please contact this office.
Yours truly, mrr JJH/CWG l
attachments:
1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions l
cc:
(See Next Page)
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220042 g
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9701220265 961231 PDR ADOCK 05000416 R
- PDR,
January 15, 1997 GNRO-97/00005 Page 2 of 3 l
cc:
Mr. D C. Hintz (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. J. E. Tedrow (w/a)
Mr. H. L. Thomas (w/o)
Mr. Leonard J. Callan (w/a)
Regional Administrator U S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Ariington, TX 76011 l
Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 l
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. to GNRO-97/00005 DOCKET NO 50-416 DATE 01/14/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 OPERATING STATUS 1.
Unit Name: GGNS UNIT 1 2.
Reporting Period: December 1996 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): 1228 MWE 7.
Maximum Dependable Capacity (Net MWe):
1179 MWE l
8.
If changes occur in Capacity Ratings (Items 3 l
through 7) Since Last Report. Give Reason:
l 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 8.784
,_106.960
- 12. Number of Hours Reactor was Critical 744.0 7.788.0 87.979.0
- 13. Reactor Reserve Shutdown Hours 0
0 0
l
- 14. Hours Generator On-Une 733.6 7.698.4 84.876.9_ _
- 15. Unit Reserve Shutdown F.J' irs 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2.539.126 28.885.504 303.119.036
- 17. Gross Electrical Energy Generated (MWH) 860.729 9.602.740 97.271.931
- 18. Net Electrical Energy Generated (MWH) 826.736 9.224.700 93.224.345
- 19. Unit Service Factor 98.6 87.6 81.1
- 20. Unit Availability Factor 98 1 87.6 81.1
- 21. Unit Capacity Factor (Using MDC Net) 94.3 89.3 79.4
- 22. Unit Capacity Factor (Using DER Net) 88.9 84.0 72.5
- 23. Unit Forced Outage Rate 1.4 3.9 6.3
- 24. Shutdowns Scheduled Over Next 6 Months (Type, t., :. 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):
Forecast Achieved INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85
j t
- to GNRO-97/00005 DOCKET NO 50-416 DATE 01/14/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 MONTH December 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 181 17 1280 2
123 18 1283 3
297 19 1285 I
4 571 20 i286 l
5 769 21 1247 6
1192 22 1262 7
1048 23 1253 8
1253 24 1275 9
1264 25 1283 10 1255 26 1271 11 1233 27 1254 12 1241 28 1246 13 1254 29 1252 14 1256 30 1253 15 1254 31 1256 16 1271
F
. to i ARO-97/00005 l
UNIT SlaUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-416 UNIT NAhlE GGNS Unit l' DATE 01/14/97 COhlPLETt.O 3Y S. D. Lin "ELEPHONE (60l)437-6793 REPORT h1ONT11 December 19%
No.
Date TypefIt Dur.: tion Reason l Method Of Licensee Ewnt Sptem Code Component Cause & Corrective Action To Prevent llours (2)
- Shutting Doni Report #
(4)
Code (5)
Recurrence (CACA) l Reactor (3) 964)07 12/02/96 I-10.4 A
6 N/A N/A l4279 Core thermal power reonced to approximately 15% to trip turbine for i
repairing crack on stub tube for INI1FX301 (isolation valve for an IIP Turbine Ist-stage pressi e transmitter) 1 2
3 4
5 F: Forced Reason:
Method:
Exhibit G - Instmetions for Preparation of Exhibit 1 - Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets for Licensee Ewnt B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator T sining &
5-Reduced load Licensing Examination 6-Other F-Administrative G-Operational Error (Explain)
II-Other (Explain)
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