ML20045A955

Monthly Operating Rept for May 1993 for Grand Gulf Nuclear Station.W/930609 Ltr

ML20045A955
Person / Time
Site:	Grand Gulf
Issue date:	05/31/1993
From:	Daughtery L, Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-93-00072, GNRO-93-72, NUDOCS 9306150387
Download: ML20045A955 (5)

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June 9, 1993 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-93/00072

_ Gentlemen: l In accordance with the requirement of Technical Specification 6.9.1.10, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for May 1993.

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

Yo s truly,

' s 0 - _ __

.- . Hutchinson Vice President - Operations GGNS CRH/TMC/cg t attachments: 1. Operating Status

2. Average Daily Power Level

3. Unit Shutdown and Power Reduction '

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June'9, 1993 GNRO-93/00072 Page 2 of 3 i

cc: Mr. R. H. Bernhard (w/a)  :!

Mr. D. C. Hintz (w/a) r Mr. R. B. McGehee (w/a)  !

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o) l

-Mr. Stewart D. Ebneter (w/a) '

Regional Administrator [

U.S. Nuclear Regulatory Commission Region II i 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 ..;

Mr. P. W. O'Connor, Project Manager  !

Office of nuclear Reactor Regulation U.S. Nucleatr Regulatory Commission Mail.Stop 13H3 i Washington, D.C. 20555 F

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DOCKET NO 50-416 DATE 06/08/93 COMPLETED BY L. F. Dauchtery-TELEPHONE (601) 437-2334 OPERATING STATUS

1. Unit Name: GGNS UNIT 1

-2. Reporting Period: May 1993

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): 1190 MWE

7. Maximum Dependable Capacity (Net MWe): 1143 MWE

8. If changes occur in Capacity Ratings (Items 3 through 7) Since Last Report. Give Resason:

N/A

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 3,623 75.519

'12. Number of Hours Reactor was Critical 744.0 3.623.0 61,169.1

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 744.0 3623.0 58,836.7-

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2,801.943. 13,719.038 205,959,178 17.. Gross Electrical Energy Generated (MWH) 898,390- 4,461,442 65,543,274

18. Net Electrical Energy Generated (MWH) 863.413 4,290.844 62,758,768^-

19. Unit Service Factor 100.0~ 100.0 80.4

-20. Unit Availability Factor 100.0 100.0 80.4-21~. Unit Capacity- Factor (Using MDC Net) 101.5 103.6 77.4 22._ Unit Capacity Factor (Using DER Net) 92.8 94.8 70.2 23._ Unit Forced Outage Rate 0 0 5.9 24._ Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of-Each):

Beain Refuelina Outaae-6 on 10/08/93 for an estimated duration of 46 days.

25. If Shut Down At End of Report Period. Estimated Date of Startup:

26.l 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

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DOCKET NO' 50-416 l 4

DATE 06/08/93 COMPLETED BY L. F. Dauchtery ,

TELEPHONE (601) 437-2334  ;

1 MONTH May 1993 Day. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

'I 1 1138 17 1175

'2 1182 18 _. 1136 3- 1190 19 1185 4 1188 20 1191 l[

l 5 1179 21 1193 i 6 1177 22 1185- ,

'I' 7 1177 23 1184 i

8 1163 24 1180 i 9 1175 25 1178

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10 1151 26 1165

l 11 1188 27 1177  !

12 1122 28 1174 l 13- 1188 29 1136  !

.14- 1188 30 1174 )

15 903 31 1176 i 16- 1059 N/A  !

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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO 50-416 DATE 06/08/93 COMPLETED BY L. F. Daughtery TELEPHONE (601) 437-2334-REPORT MONTH May 1993 No. Date Type Duration Reason Method of Licensee System component cause &

(1) Hours (2) Shutting Event Code Code Corrective Down Report # (4) (5) Action to Reactor Prevent (3) Recurrence 93- 05/15/93 S 32.2 B 5 NA NA NA Reactor. thermal 004 power reduced to approximately 60% for control rod sequence exchange.

1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions

-S: Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual' Scram Entry Sheets for Licensee-B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued File (NUREG-0161)

D-Regulatory Restricting 5-Reduced load E-Operator Training & 6-Other Licensing Examination 5 F-Administrative Exhibit 1-Same Source G-Operational Error (Explain)

H-Other (Explain)

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