ML20199K061

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Monthly Operating Rept for Oct 1997 for Grand Gulf Nuclear Station,Unit 1
ML20199K061
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/31/1997
From: Hagan J, Lin S
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-97-00110, GNRO-97-110, NUDOCS 9711280306
Download: ML20199K061 (5)


Text

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4 Josep5 J. Hagan November 14, 1997

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or cuino:> ear stam U.S. Nuclear Regulatory Commission Mail Station P1 137 Washington, D.C. 20555 Attention:

Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Dccket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-97/00110 Gentlemen:

In accordance with the requirement of Technical Specification 5.6.4, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nu lear Station Unit 1 for October

1997, if you have any questions or require additional information, please contact this office.

Yours truly, J

JJH/SDileg attachments: 1.

parating Status l

2.

Average Daily Power Level

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't Shutdown and Power Reductions 7

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GNRO-97/00110 i Page 2 of 3 -

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

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

Mr. Jager Smith (w/a)

Mr. H. L Thomas (w/o)

Ms. K. D. Weaver (w/a)

' Mr. Leonard J. Callan (w/a)

Regional Administrator '

U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mall Stop 13H3 Washington, D.C. 20555

Attachment i to GNRO 97/00110 DOCKET NO 50-416 DATE 11/06/97 COMPLETED BY S. D. Lin

)

TELEPHONE (601) 437-6793 OPERATING STATUS 1.

Un:t Name: GGNS UNIT 1 2.

Reporting Period: October 1997 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 Capacit';(Gross MWe): 1250 MWE F

7.

Maximum Dependable Capacity (Net MWe):

1200 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 Ihis Month Yr to Date Cumulative 11, Hours in Reporting Period 745 7.296 114.256

12. Number of Hours Reactor was Critical 745.0 7.296.0 95.275.0
13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 745.0 7.296.0 92.172.9
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.852.063 27.780.487 330.899.523
17. Gross Electrical Energy Generated (MWH) 961.980 9.370.341_

106.642.272 3

18. Net Electrical Energy Generated (MWH) 925.513 9.012.843 _ 102.237.188
19. Unit Service Factor 100.0 100.0 82.4
20. Unit Availability Factor 100.0 100.0 82.4
21. Unit Capacity Factor (Using MDC Net) 103.5 102.9 61 1
22. Unit Capacity Factor (Using DER Net) 99.4 98.8 74.1
23. Unit Forced Outage Rate 0.0 0.0 5.8
24. Shutdowns Scheduled Over Next 6 Months (Type, Daia, and Duration of Each):

Refuelino Outaoe #9 beoinnino on 04/11/98 @0000 hour for 32 Days

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

N/A

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

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.e a.:

- to GNRO 97/00110 DOCKET NO 50-416 DATE 11/10/97 COMPLETED BY S. D. Lin TELEPHONE (801) 437-6793 MONTH October 1997 DAY. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 1 1232 17 1257 2

1240 18 1240 3

1245 19 1256 4

1216 20 1245 5

1232-21 1243 6

1230 22 M56 7

1229 23 1249 8

1228 24 1233 9

1225 25 1225 10 1228 26 1254 11 1232 27 1265 12 1230 28 1266 13 1238 20 1259 14 1254 30 1252-15 1256 31 1242 16 1257

o v

. to GNRO-97/OO11C -

DOCKET NO 50-416 DATE

-11/10/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 UNIT SHUTDOWNS AND POuTR FIDUC110NS REPORT MONTH October 1997 No.

Date Type (1)

Duration Reason Method Of Licensee Event System Code Component Cause & Corr:ctive Action To Prevent Hours (2)

Shutting Down Report #

(4)

Code (5)

Recurrence (C&CA)

Reactor O)

None 1

2 3

'4 5

F: Forced Reason:

Method:

Exhibit G - Instructions for Prepara: ion of Exhibi~ l - Same Source l

S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets for Licensee Event B-Maintenance or Test 2-Manual Sda Report (LER) File (NUREG4)l61)

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)

.