ML20141E354
| ML20141E354 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 04/30/1997 |
| From: | Hagan J, Lin S ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-97-00038, GNRO-97-38, NUDOCS 9705200412 | |
| Download: ML20141E354 (5) | |
Text
Entorgy perations, Inc.
Port Gibson. MS 39150 Tel 601437 6408 Fax 601437 2795 Joseph J. Hagan V>ce President Operat;Qns Grand Gulf Nuclear Station May 13, 1997 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attention:
Document Contro! Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-97/00038 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 April 1997.
If you have any questions or require additional information, please contact this office.
Yours truly, 1
JJH/CWG
/
attachments: 1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions cc:
(See Next Page)
/
9705200412 970430 i
PDR ADOCK 05000416:
R PDR 1
3
, ~ s1
- 8:
May 13. 1997 j
'GNRO-97/00038
,Page 2 of 3 I
i cc:
Mr. D. C. Hintz (w/a)'
i
, Mr. R. B. McGehee (w/a) l Mr. N. S. Reynolds (w/a) l Mr. J. E. Tedrow (w/a)
- Mr. H. L Thomas (w/o) '
7 Mr. Leonard J. Callan (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
- 4 Office of Nuclear Reactor Regulation '
l U.S. Nuclear Regulatory Commission Mail Stop 13H3--
Washington, D.C. 20555 q
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DOCKET NO.
50-416 DATE 05/05/97
'l COMPLETED BY S.D.Lin TELEPHONE (601) 437 6793 OPERATING STATUS 1.
Unit Name: GGNS UNIT 1 4
2.
Reporting Period: APRIL 1997 3.
Licensed Thermal Power (MWt): 3833 MWT -
4, Nameplate Rating (Gross MWe): 1372.5 MWE 5.
Design Electrical Rating (Net MWe): 1250 MWE l
6.
Maximum Dependable Capacity (Gross MWe): _1250 MWE
~
7.
Maximum Dependable Capacity (Net MWe):
1200 MWE 8.
If changes occur in Capacity Ratings (ltems 3 through 7) Since Last Report. Give Reason:
N/A 9.
Power Level To Which Restricted, if Any (Net MWe):
N/A 4
- 10. Reasons For Restrictions, if Any:
N/A This Month Yr to Date Cumulative
)
- 11. Hours in Reporting Period 719 S.879 109.839
- 12. Number of Hours Reactor was Critical 719 & _
2.879.0 90.858.0
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 719.0 2.879.0 87.755.9
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2.753.455 11.001.320 314.120.356 l
- 17. Gross Electrical Energy Generated (MWH) 939,333 3 764.589 101.036.520 1
4:
- 18. Net Electrical Energy Generated (MWH) 904.392 3.622.971 96.847.316
- 19. Unit Service Factor 100.0 100.0 81.7
- 20. Unit Availability Factor 100.0 100.0 81.7 i
- 21. Unit Capacity Factor (Using MDC Net) 104.8 104.9 80.2 n
- 22. Unit Capacity Factor (Using DER Net) 100.6 100.7 73.3
- 23. Unit Forced Outage Rate 0.0 0.0 6.1
' 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 i
INITIAL ELECTRIC!TY 10/20/84 i
i COMMERCIAL OPERATION 07/01/85 I
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4 4 to GNRO-97/00038 j
DOCKET NO 50-416 DATE 05/05/97 COMPLETED BY S.D.Lin TELEPHONE (601) 437-6793.
i MONTH Aoril1997 -
DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1
1263 17-1265 l
2 1260 18 1267 l
3 1256 19 1243 4
4 1244 20 1249 5
1234 21 1243 j
6 1252 22 1250 7
1264 23 1261 8
1267 24 1263 9
1264 25 1264 10 1261 26 1256 11 1256 27 1250 i
12 1265 28 1259 13 1274 29 1260 14 1272 30 1247 15 1267 31 N/A 16 1262 l
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' Attachment 3 to GNRO-97A)0038 DOCKET NO.~
50-416 UNIT NAME GGNS Unit I DATE 05A)5/97 COMPLETED BY S, D. Lin ^
TELEPHONE (601)437-6793 REPORT MONT11 April 1997 No.
Date -
Type (1)
Duratum Reason Method Of lxensee Event System Code Component Cause & Conective Action To Prevent Hours (2)
Shutting Donn Report #
(4)
Code (5)
Recunence(CACA)
Reactor (3)
None
- 1 2
3 4
5 F: Forced Reason:
Method.
Exhibit G - Instructions for Preparation of ExluWt 1-Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets forIxensee Ewnt
+
B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG4)l61) -
C-Refueling 3-Automatic Scram D-Regulatory Roan;Gies 4-Continued E-Operator Training & -
5-Reducedload Licensing Examination 6 Other F-Administratin Goperational Error (Ex1 ain) d H-Other (Explain) t T
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