ML20058M600

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Monthly Operating Rept for Nov 1993 for GGNS Unit 1
ML20058M600
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 11/30/1993
From: Daughtery L, Hutchinson C
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-93-00157, GNRO-93-157, NUDOCS 9312210040
Download: ML20058M600 (5)


Text

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A_ENTERGY Enttr;y Operctirne,Inc.

- se fixt Gason, MS. 39150 Tel 601437 2800 C. R. Hutchinson vec Preet Operatoris Gram G# b:iaar staton December 14, 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-93/00157 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 November 1993.

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

Yours truly,

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l attachments:

1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Power Reduction cc:

(See Next Page) 2100: G H

9312210040 931130 p

PDR ADOCK0500g6 g

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December.14, 1993 GNitO-93/00157 Page 2 of 3

/

cc:

Mr. R. H. Bembard (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 l

U.S. Nuclear Regulatory Commission Region 11 l

101 Marietta St., N.W., Suite 2900 l

Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission i

Mail Stop 13H3 Washington, D.C. 20555 l

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a DOCKET NO 50-416' l

DATE 12/07/93 COMPLETED BY-L. F. Dauohterv TELEPHONE (601) 437-2334-OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 2.

Reporting Period: November 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 i

8.

If changes occur in Capacity Ratings (Items 3

(

through 7) Since Last Report. Give Resason:

N/A j

j 9.

Power Level To Which Restricted, if Any (Net MWe):

N/A J

10. Reasons For Restrictions, if Any:

N/A l

This Month Yr to Date'

~ Cumulative'

11. Hours in Reporting Period 720 8.016 79.912 l
12. Number of Hours Reactor was Critical 94.7 6.427.1 63.973.3
13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 0

6.183.2' 61.396.9 i

15. Unit Reserve Shutdown Hours 0

0-0-

16. Gross Thermal Energy Generated (MWH) 0 23.276.782 215.516.922
17. Gross Electrical Energy Generated (MWH) 0 7.477.150 68.558.982
18. Net Electrical Energy Generated (MWH) 0 7.185.016 65.652.940

{

19. Unit Service Factor 0

77.1 79.1

20. Unit Availability Factor 0

77.1 79.1 l

21. Unit Capacity Factor (Using MDC Net) 0 78.4 76.2 t
22. Unit Capacity Factor (Using DER Net) 0 71.7 69.2 i
23. Unit Forced Outage Rate 0

8.8 6.5 l

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

I

25. If Shut Down At End of Report Period. Estimated Date of Startup: 12/04/93
26. Units in Test Status (Prior to Commercial Operation).

Forecast -

A_g,higvqd

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INITIAL CRITICALITY 08/18/82 l

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

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DOCKET NO 50-416 l

DATE 12/07/93 l

COMPLETED BY L. F. Davahtery TELEPHONE (601) 437-2334 l

MONTH November 1993 l

Day AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

1 6

0 22 0

l 7

0 23 0

8 0

24 0

l 9

0 25 0

l l

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 N/A 16 0

N/A

_ ~.

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416 UNIT NAME I

DATE 11/03/91 COMPLETED BY L.F.Dat ghtery TELEPilONE 601-43'/-2334 REPORT MONT11 NOVEMBER 1993 NO Date Type (1)

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

Shutting Event Report #

(4)

Code Prevent Recmrence (C&CA)

Down Reactor (5)

(3)93-008 09/28/93 F/S 1232.6 A/C 1

93-009 AD EDR Continued Refueling Outage 6.93-009 11/07/93 F

250.0 11 4

NA NA NA RFO6 extended tecause of unplanned work items (e g., replacement ofjet pumps) and more repair time for planned items.

934)l0 11/27/93 F

40.4 D

1 NA NA NA Reactor was shutdown while critical because sulfate concentration exceeded EPRI limit.

I 2

3 4

5 F: Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Exlubit 1 - Same Source S: Scheduled A-Equipment Faihire (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-Cominued E-Operator Training &

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

II-Other (Explain) 1

...