ML20195F480
| ML20195F480 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/31/1998 |
| From: | Lin S, Venable J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-98-00093, GNRO-98-93, NUDOCS 9811200007 | |
| Download: ML20195F480 (5) | |
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Entsrgy operations, Inc.
h P. O. Box 756 Port Gbson, MS 39150 Tel 601437 2129 l
Joseph E. Venable General Manager Plant Operatons November 11, 1998 l.
l 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-98/00093 t
Gentlemen:
l 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 October 1998.
- If you have any questions or require additional information, please contact this office.
Yours truly, M
l JEV/SDUcg attachments: 1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions cc:
(See Next Page) l-i
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PDR ADOCK 05000416 1(
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D GNRO-98/00093 Page 2 of 3,
cc:
Mr. D. C. Hintz (w/a)
Mr. N. S. Reynolds (w/a)
Mr. Jager Smith (w/a)
- Mr. H. L. Thomas (w/o)
Ms. K. D. Weaver (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 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 I
c
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Attachment I to GNRO-98/00093 DOCKET NO 50-416 DATE 11/05/98 COMPLETED BY S. D. Lin TELEPHONE (601)437-6793 OPERATING STATUS
.l.
Unit Name: GGNS UNIT 1 2.
Reporting Period: October 1998 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): 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 745 7,296 123,016
- 12. Number of Hours Reactor was Critical 745.0 6,320.5 103,059.5
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. - Hours Generator On-Line 745.0 6,178.3 99,815.2
- 15. Unit Reserve Shutdown Hours 0
0 0
. 16. Gross Thermal Energy Generated (MWH) 2,801,303 22,871,668 359,281,963
- 17. Gross Electrical Energy Generated (MWH) 950,169 7,649,490 116,168,290
- 18. Net Electrical Energy Generated (MWH) 913,924 7,349,300 111,391,209
- 19. ' Unit Service Factor 100.0 84.7 82.8
- 20. Unit Availability Factor 100.0 84.7 82.8
- 21. Unit Capacity Factor (Using MDC Net) 101.9 83.8 81.5
- 22. Unit Capacity Factor (Using DER Net) 98.1 80.6 75.0
- 23. Unit Forced Outage Rate 0.
3.9 5.6
- 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):
Forecast Achieved INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85
- Items 11 through 18 are cumulative results since initial electricity
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b E to GNRO-98/00093 a
- 6 -
l DOCKET NO 50-416
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DATE 1I/05/98 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 MONTH: October 1998 DAY AVERAGE DA?LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1227
' 17 1246 l'
2-1230 18 1243 i
3 1161 19 1251 l-
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4 1240 20 1259 l
5 1237 21 615 l-6 1239 22.
1241
.7 1256' 23 1272 8
'1261~
24 1227 i
l-9-
1265 25 1265 l'
-10
-1240 26 1259 11 1259' 27 1260
- 12" 1256 28 1260 13 -
'1255 29 1254
-14 1255 30 1251 l-
.15 1250 31 1251 l
_16 1242
=
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. to GNRO-98/00093 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MON 1H October 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)
Recurrence (C&CA)
Reactor (3)98-011 10/21/98 F
0.
A 6
N/A N/A N/A Power reduced to approximately 50%
when circulating Water Pump "A" tripped because of burned electrical lead.
I 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) i I
h