ML20072F996

Monthly Operating Rept for July 1994 for GGNS Unit 1

ML20072F996
Person / Time
Site:	Grand Gulf
Issue date:	07/31/1994
From:	Hutchinson C, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-94-00104, GNRO-94-104, NUDOCS 9408240158
Download: ML20072F996 (5)

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T C. R. Hutchinson t

August 14, 1994

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.m 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-94/00104 Gentlemen:

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 July 1994.

In the May and June Monthly Operating Report, Unit Shutdowns and Power Reductions #94-005 was reported as Forced. This should be reported as Scheduled, if you have any questions or require additionalinformation, please contact this office.

Yours truly, 6f?NW J

LV CRH/TMC attachments:

1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Power Reductions cc:

(See Next Page)

• 6 's e

- o 9408240158 940'/31 PDR ADDCK 05000416 R

PDR

August 14, 1994

. GNRO-94/00104 Page 2 of 3 cc:

Mr. R. H. Bernhard (w/a)

Mr. D. C. Hintz (w/a)

Mr. R. B. McGehee (w/a)

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

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

Mr. Stewart D. Ebneter (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region Il 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555

. m

. to GNRO-94/00104 r

DOCKET NO 50-416 DATE 08/09/94 COMPLETED BY S. D. Lin TELEPHONE

[6. 01) 437-6793 MONTH luly 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1167 17 757 2

1165 18 757 3

1167 19 748 4

1164 20 779 5

1163 21 974 6

1164 22 1167 7

1164 23 1156 8

1128 24 1163 9

1173 25 1163 10 1176 26 1161 11 1174 27 1143 12 1157 28 1176 13 1152 29 1178 14 1117 30 1171 15 1168 31 1176 16 751

P Attachment I to GNRO-94/00104 DOCKET NO 50-416 DATE 07/06/94 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6791 OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 2.

Reporting Period: July 1994 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 Wh;ch 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 5.087 85.743

12. Number of Hours Reactor was Critical 744.0 4.933.1 69.619.7

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.0 4.895.0 66.954.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.675.560 18.221.904 236.039.475

17. Gross Electrical Energy Generated (MWH) 847.804 5 887.614 75.195.118

18. Net Electrical Energy Generated (MWH) 811.636 5.654.257 72.025.644

19. Unit Service Factor 100.0 96.2 80.2

20. Unit Availability Factor 100.0 96.2 80.2

21. Unit Capacity Factor (Using MDC Net) 95.4 97.3 77.6

22. Unit Capacity Factor (Using DER Net) 87.3 88.9 70.5

23. Unit Forced Outage Rate 0.0 3.8 6.3

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

- Attachment 3 to GNRO-94!0018(

UNITSHUTDOWNS AND POWER REDUCTIONS i

DOCKET NO.

50-416

• UNTT NAME '

GGNS Uriit I DAili OM)9/94 COMPLETED BY S. D. Lin TELEPHONE (6011437-6793 REPORT MONTH July 1994 t.

No.

Date Type (1)

Duration Reason Method Of Licensee System Code Component Cause & Correcuve Action To Hours (2)

Shuttmg Event Report #

(4)

Code Prevent Recurrence (C&CA)

Down Reactor (5)

(3)

I 94-006 940716 S

I38.0 B

5 N/A N/A N/A Power was reduced to approximately 70 i

% for control rod sequence exchange.

Control rod scram time testmg was performed during the low power i

operation.

1 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 i

E-Operator Training &

5-Reduced load Licensing Examination 6-Other l

F-Administrative I

G-Operational Error (Explain) f H-Other (Explain) i 4

1 a

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