ML20065L107

Monthly Operating Rept for Mar 1994 for Grand Gulf Nuclear Station Unit 1

ML20065L107
Person / Time
Site:	Grand Gulf
Issue date:	03/31/1994
From:	Hutchinson C, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-94-00057, GNRO-94-57, NUDOCS 9404200290
Download: ML20065L107 (5)

Text

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Entergy Operctions,Inc.

_ ENTERGY eo eex7se 1

Fbrt G,bson MS 3940 l

Td 601437 2800 C. R. Hutchinson -

w e Preson cwun Gm> Gulf M&ar Swm

-April 15, 1994 U.S. Nuclear Regulatory Commission Mail Station P1-137 j

Washington, D.C. 20555 l

Attention:

Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-94/00057 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 March 1994.

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

Yours truly, i

r Id CRH/TMC attachments:

1.

Operating Status l

2.

Average Daily Power Level 3.

Unit Shutdown and Power Reductions cc:

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April 15,1994 GNRO-94/00057 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 li 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

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Mail Stop 13H3 Washington, D.C. 20555

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2 Attachment I to GNRO-94/00057 DOCKET NO HQ-416 DATE 04/11/94 COMPLETED BY S. D. Lin j

TELEPHONE (601) 437-6793 l

I OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 2.

Reporting Period: March 1994 3.

Licensed Thermal Power (MWt): 3833 MWT 4.

Nameplate Rating (Gross MWe): 1372.5 MWE j

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 l

This Month Yr to Date Cumulative

11. Hours in Reporting Period 744 2.160 82.816 l

12. Number of Hours Reactor was Critical 624.1 2.040.1 66.726.7 l

13. Reactor Reserve Shutdown Hours 0

0 0

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14. Hours Generator On-Line 624.1 2.040.1 64.099.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.363.934 7.747.366 225.564.937

17. Gross Electrical Energy Generated (MWH) 769.989 2.541.518 71.849.022

18. Net Electrical Energy Generated (MWH) 740.917 2.446.612 68.817,999

19. Unit Service Factor 83.9_

94.5 79.6

20. Unit Availability Factor 83.9 94.5 79.6

21. Unit Capacity Factor (Using MDC Net) 87.1 99.1 76.9 j

22. Unit Capacity Factor (Using DER Net) 79.7 90.6 69.9 l

23. Unit Forced Outage Rate 16.1 6.0 6.5

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:

Reactor Startuo - 4/4/94

26. Units in Test Status (Prior to Commercial Operation).

Forecast Achieved INITIAL CRITICALITY 08/18/82 i

INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85 l

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'a 1 to GNRO 94/00057 i

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DOCKET NO 50-416 i

DATE 04/11/94

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COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 MONTH March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net)

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1 1127 17 1210 l

l 2

1214 18 1198 3

1215 19 1181 4

1204 20 1191 5

1200 21 1194 6

1198 22 1202 l

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7 1194 23 1186 l

8 1191 24 1150 l

9 1186 25 1204 10 1219 26 964 11 1215 27 11 12 1212 28 0

13 1205 29 0

14 1204 30 0

l 15 1196 31 0

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16 1209 I

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Attschment III to GNRO-94/00057 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416 UNIT NAME GGNS Unit I DATE 04/08/94 COMPLETED BY S. D. Lin TELEPHONE (6011437-6793 REPORT MONTli MARCII 1994 NO Date Type (I)

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

Shutting Event Report #

(4)

Code Prevent Recurrence (C&CA)

Down Reactor (5)

(3)94-002 03/:tv94 S

14.8 B

5 N/A N/A N/A Reactor thermal power reduced to approximately 70% for control rod sequence exchange 94-003 03/27/94 I-119 9 A

2 944XM CD ROD Reactor shut down per Techmcal Specifications on more than 20% of the 10% sampled control rods failmg scram time test.

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 E-Operator Training &

5-Reduced load Licensing Examination 6-Other F-Administratn e G-Operational Error (Explain)

H-Other (Explain)

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