ML20148L259

Monthly Operating Rept for May 1997 for GGNS Unit 1

ML20148L259
Person / Time
Site:	Grand Gulf
Issue date:	05/31/1997
From:	Hagan J, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-97-00053, GNRO-97-53, NUDOCS 9706190181
Download: ML20148L259 (6)

Text

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l EntIrgy oper tions,Inc.

y yg PO. Box 756 1E Port Gcson. MS 39150 Tel 601437 6408 Fax 601437 2795

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Joseph J. Hagan Vice President Operatrons June 13, 1997 Grand Gulf Nuclear Station l

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l U.S. Nuclear Regulatory Commission l

Mail Station P1-137 Washington, D.C. 20555 i

l Attention:

Document Control Desk l

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SUBJECT:

Grand Gulf Nuclear Station l

Unit 1 Docket No. 50-416 License No. NPF-29 l

Monthly Operating Report GNRO-97/00053 i

Gentlemen:

In accordance with the requirement oi Technical Specification 5.6.4, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for May 1997.

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

Yours truly, hI ag.

JJH/cwg attachments:

1.

Operating Status

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Average Daily Power Level r'lA

%g 3.

Unit Shutdown and Power Reductions

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cc:

(See Next Page) l l

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9706190181 970531 m

i PDR ADOCK 05000416 '

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R PDR 100040

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June-13, 1997 GNRO-97/00053 Page 2 of.3 1

l cc:

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

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

Mr. Jager Smith (w/a)

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

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

Mr. Leonard J. Callan (w/a) l Regional Administrator U.S. Nuclear Regulatory Commission i

Region IV 611 Ryan Plaza Drive Suite 400 i

Arlington, TX 76011 i

i Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 l

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- to GNRO-97/00053 l

DOCKET NO 50-416 DATE 06/06/97 l

COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 OPERATING STATUS I

1.

Unit Name: GGNS UNIT 1 2.

Reporting Period: MAY 1997 3.

Licensed Thermal Power (MWt): 3833 MWT 4.

Nameplate Rating (Gross MWe): 1372.5 MWE 5.

Design Electrical Rating (Net I.iWe): 1250 MWE 6.

Maximum Dependable Capacitv (Gross MWe): 1250 MWE 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 This Month Yr to Date Cumulative

11. Hours in Reporting Period 744 3,623 110,583

12. Number of Hours Reactor was Critical 744.0 3,623.0 91,602.0

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744,0 3,623.0 88,499.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1 809,958 13,811,278 316,930,314

17. Gross Electrical Energy Generated (MWH) 946,539 4,711,128 101,983,059

18. Net Electrical Energy Generated (MWH) 910.522 4,533,493 97,757,838

19. Unit Service Factor 100.0 100.0 81.8

20. Unit Availabhity Factor 100.0 100.0 81.8

21. Unit Capacity Factor (Using MDC Net) 102.0 104.3 80.3 l

22. Unit Capacity Facto: (Using DER Net) 97.9 100.1 73.5 l

23. Unit Forced Outage Rate 0.0 0.0 6.0

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

None

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

N/A

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

l Forecast Achieved l

INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85 c.

. - - ~ -

- -... - = -.

,. to GNRO-97/00053 DOCKET NO 50-416 DATE 06/06/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 j

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MONTH May 1997 l

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

(MWe-Net) i 1

1251 17 1093 2

1237 18 1225 3

1232 19 1236 l

4 1261 20 1235 5

1258 21 1246 l

l 6

1249 22 1109 l

7 1247 23 1241 l

8 1242 24 1238

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9 1247 25 1235 l

10 1254 26 1228 l

11 1257 27 1227 12 1135 28 1238 13 1238 29 1059 14 1244 30 1237 15 1247 31 1245 16 1248 l

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. to GNRO-97M0053. ',

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416 i

UNIT NAME GGNS Unit i DATE 06M6/97 COMPLETED BY S. D. Lin TELEPHONE (6011437-6793 l

f REPORT MONTH May 1997 i

l Type (1)

Duration Reason Method Of Licensee Esent System Code Component Cause & Corrective Action To Prevent No.

Date Hours (2)

Shutting Down Report #

(4)

Code (5)

Recurrence (C&CA)

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l Reactor (3) l Nonc 1

2 3

4 5

F: Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Exlutit 1 - Same Source i

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-Reducef load

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Licensing Examination 6-Other e

F-Administrative G-Operational Error (Explain)

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H-Other (Explain) f r

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NRC SUBMITTAL CERTIFICATION FORM (Miscellaneous) l t

i Letter Number (List GNRO, GIN, GEXO, etc.)

GNRO-97/00053 C. W. Gunn 064)6/97 Document Originator Date t

11.

Certification: Responsible Sechon/ Organization Enaineerina Support

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PAGE! PARAGRAPH NO.

SENTENCE NUMBER (S)

1. BASIS COMMENTS Attachments 1,2, & 3 ALL Data and calculations based on GGNS Unit

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1 switchboard Log (PDS), Pine Bluff EMS, Rx. Eng. Fuel Accounting Program and

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STA Log entries.

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1. BASIS:

1)

Indicate when an action was or will be done (date) and how.

Y AM kkf7 RMsiblesechon Individual

' Date i

2)

If statement of fact list supporting document (s) i.e., UFSAR, 43 97 P&lD, Procedure, etc.

Responsible'Sechon Supervisor [$ ate / ~ '

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3)

May be a statement or conclusion which is only suppcrted l

by engineering judgment which must be described under basis.

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• Signature indicates certification of the accuracy of indicated portions of the document. Document may be certified with comments.

NOTE: Use separate sheet for each sections / organization

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