ML20106H085

Monthly Operating Rept for Feb 1996 for Grand Gulf Nuclear Station,Unit 1

ML20106H085
Person / Time
Site:	Grand Gulf
Issue date:	02/29/1996
From:	Hutchinson C, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-96-00025, GNRO-96-25, NUDOCS 9603200172
Download: ML20106H085 (5)

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March 14, 1996 U.S.14uclear 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-96/000 2 5 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 February 1996.

If you have any questions or require additional information, please contact this office.

Yours truly,

~

/

CRH/TMC attachments:

1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Power Reductions cc:

(See Next Page) 20001A 9603200172 960229 f)

PDR ADOCK 05000416 R

PDR f

l 1

March 14, 1996 GNRO-96/00025 j

Page 2 of 3 i

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 l

U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 i

1 Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 i

i 4

l 5

Attachmint 1 to GNRO-96/OOO25 DOCKET NO 50-416 DATE 03/07/96 COMPLETED BY S.D.Un TELEPHONE (6011 437-6793 OPERATING STATUS

)

1.

Unit Name: GGNS UNIT 1 2.

Reporting Period: Februarv 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): 1222 MWE 7.

Maximum Dependable Capacity (Net MWe): 1173 MWE

{

8.

If changes occur in Capacity Ratings (items 3 1

through 7) Since Last Report. Give Reason:

1 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 696 1440 99.616

12. Number of Hours Reactor was Critical 696.0 1440.0 81.631.0

13. Reactor Reserve Shutdovvn Hours C

0 0

14. Hours Generator On-Line 696.0 1440.0 78.618.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.632.937 5.457.713 279.691.245

17. Gross Electrical Energy Generated (MWH) 884.197 1.835.490 89.50a.681

18. Net Electrical Energy Generated (MWH) 849.403 1./63.682 85.763.327

19. Unit Service Factor 100.0 100.0 80.8

20. Unit Availability Factor 100.0 100.0 80.8

21. Unit Capacity Factor (Using MDC Net) 104.0 104.4 78.9

22. Unit Capacity Factor (Using DER Net) 97.6 98.0 71.8

23. Unit Forced Outage Rate 0.0 0.0 6.4

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):

Forecast Achieved INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85

AttichmInt 2 to GNRO-96/OOO25 DOCKET NO 50-418 DATE 03/07/98 COMPLETED BY S. D. Lin TELEPHONE (8011 437-8793 MONTH February 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1254 17 1248 2

1254 18 1238 3

1258 19 1229 4

1259 20 1228 5

1251 21 1222 6

1245 22 1221 7

1234 23 1220 8

1217 24 1228 9

1225 25 1223 10 1208 26 1213 11 1238 27 1214 12 1248 28 1243 13 891 29 1251 14 1149 30 N/A 15 1235 31 N/A 16 1251 l

1 l

I

. to GNRO-96/00025,

• UNIT SIIUTDOWNS AND POWER REDUCFIONS DOCKET NO.

50-416 UNITNAME GGNS Unit 1, DATE 03/07M6 COMPLETED BY S. D. Lin TELEPHONE (601M37-6793' REPORT MONTil Jebruary 1996 No.

Date Type (1)

Duration Reason Method Of Licensee System Code Component Cause & Corrective Action To flours (2)

Shutting Down Es ent Report #

(4)

Code Prevent Recurrence (C&CA)

Reactor (5)

(3) l 96-001 02/13/96 S

0.

B 6

N/A N/A N/A Reactor powtr reduced to approximately 60% for control rod sequence exchange.

I 2

3 4

5 F: Forced Reason:

Method:

t ibit 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-Manua: Scram Report (LER) File (NUREG-0161)

C-Refueling 3-Autom.* tic 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