ML20082H575

Monthly Operating Rept for Mar 1995 for Grand Gulf Nuclear Station

ML20082H575
Person / Time
Site:	Grand Gulf
Issue date:	03/31/1995
From:	Hutchinson C, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-95-00051, GNRO-95-51, NUDOCS 9504170229
Download: ML20082H575 (5)

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1. _ ENTERGY

-- eo eox758 Pon Gbson, MS 39150

.-f . Tel 601437 2800

. a C. R. Hutchinson Vre PrecAmt Owatre Graiv) Gulf Nucear S' anon April 10, 1995 U.S. Nuclear Regulatory Commission Mail Station P1-137

- Washington, D.C. 20555 Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit i Docket No. 50-416 Ucense No. NPF-29 Monthly Operating Report GNRO-95/000 51 Gentlenen:

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 i for March 1995.

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

Yours truly, g [

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CRH/TMC attachments: 1. Operating Status

2. Average Daily Power Level

3. Unit Shutdown and Power Reductions cc: (See Next Page) l

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k-Apr'il 10, 1995

' GNRO-95/00051 Page 2 of 3 cc: M . O. 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. Stewart D. Ebneter (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region ll 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 h

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Att chm:nt 1 to GNRO-95/00051 4

.' . DOCKET NO 50-416 y DATE 04/04/95 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 QPERATING STATUS

1. Unit Name: GGNS UNIT 1

2. Reporting Period: .Jdarch 1995

3. Licensed Thermal Power (MWt): 3833 MWT

4. Nameplate Rating (Gross MWe): 1372.5 MWE E. 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 Reason: 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 2.160 91.576

12. Number of Hours Reactor was Critical 719.5 2.135.5 75.286.6

13. Reactor Reserve Shutdown Hours O O O

14. Hours Generator On-Line 706.7 2.122.7 72.469.1

15. Unit Reserve Shutdown Hours O O O

16. Gross Thermal Energy Generated (MWH) 2.586.122 _2.988.522 256.832.017

17. Gross Electrical Energy Generated (MWH) 836.260 2.604.784 81.926.283

18. Net Electrical Energy Generated (MWH) 801.861 2.500.504 78.486.645

19. Unit Service Factor 95.0 98.3 81.2

20. Unit Availability Factor 95.0 98.3 81.2

21. Unit Capacity Factor (Using MDC Net) 94.3 101.3 79.0

22. Unit Capacity Factor (Using DER Net) 86.2 92.6 71.8

23. Unit Forced Outage Rate 5.Q. 1.7 6.3

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Bafuelino Outage # 7 beginnina on 04/15/94 O 0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> for a duration of 39 davs

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

I Att chm:nt 2 to GNRO-95/00051

. . DOCKET NO 50-416 DATE 04/04/95 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 MONTH _ March 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Net) (MWe-Net) 1 1172 17 28 2 1082 18 486 3 1207 19 1079 4 1049 20 1139 5 1154 21 1178 6 1060 22 1180 7 1068 23 1179 8 1210 24 1189 9 1209 25 1189 10 1205 26 1180 11 1194 27 1192 12 1189 28 1199 13 1187 29 1201 14 1192 30 1197 15 1193 31 1201 16 223

, .N Attachment 3 to GNh10-95/qMXM 1 :

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-416 UNIT NAME GGNS Unit 1 DATE 04/tM/95 COMPLETED BY S. D. Lin TELEPHONE (60lM37-6793 REPORT MONTH March 1995 No. Date Type (1) Duration Reason Method M Licensee System Code Component Cause & Corrective Action To Hours (2) Shutting Event Report # (4) Code Prevent Recurrence (C&CA)

Down Reactor (5)

(3)95-001 03/16/95 F 37.3 A 3 954XM AA SOL Reactor scram caused by pmched-wire ground fault in RCIC minimum flow valve E51F1)19 and intermittent ground of backww valve ClIFl10A which energized during Division II survedlance (halfScramexisting). Immabte corrective actions included reworkmg the ground on the RCIC valve and replacing the backup scram valve solenoid. Also, the conduit going to the solenoid was sealed to prevent moisture intrusion. A Material Nonconformance Report was initiated to address the presence of condensation in the solenoid housmg.

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)