ML20141E354

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Monthly Operating Rept for Apr 1997 for Grand Gulf Nuclear Station Unit 1
ML20141E354
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/30/1997
From: Hagan J, Lin S
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-97-00038, GNRO-97-38, NUDOCS 9705200412
Download: ML20141E354 (5)


Text

Entorgy perations, Inc.

Port Gibson. MS 39150 Tel 601437 6408 Fax 601437 2795 Joseph J. Hagan V>ce President Operat;Qns Grand Gulf Nuclear Station May 13, 1997 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attention:

Document Contro! Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-97/00038 Gentlemen:

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

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

Yours truly, 1

JJH/CWG

/

attachments: 1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Power Reductions cc:

(See Next Page)

/

9705200412 970430 i

PDR ADOCK 05000416:

R PDR 1

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8:

May 13. 1997 j

'GNRO-97/00038

,Page 2 of 3 I

i cc:

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

i

, Mr. R. B. McGehee (w/a) l Mr. N. S. Reynolds (w/a) l Mr. J. E. Tedrow (w/a)

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

7 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

4 Office of Nuclear Reactor Regulation '

l U.S. Nuclear Regulatory Commission Mail Stop 13H3--

Washington, D.C. 20555 q

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I to GNRO-97/00038

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DOCKET NO.

50-416 DATE 05/05/97

'l COMPLETED BY S.D.Lin TELEPHONE (601) 437 6793 OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 4

2.

Reporting Period: APRIL 1997 3.

Licensed Thermal Power (MWt): 3833 MWT -

4, Nameplate Rating (Gross MWe): 1372.5 MWE 5.

Design Electrical Rating (Net MWe): 1250 MWE l

6.

Maximum Dependable Capacity (Gross MWe): _1250 MWE

~

7.

Maximum Dependable Capacity (Net MWe):

1200 MWE 8.

If changes occur in Capacity Ratings (ltems 3 through 7) Since Last Report. Give Reason:

N/A 9.

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

N/A 4

10. Reasons For Restrictions, if Any:

N/A This Month Yr to Date Cumulative

)

11. Hours in Reporting Period 719 S.879 109.839
12. Number of Hours Reactor was Critical 719 & _

2.879.0 90.858.0

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 719.0 2.879.0 87.755.9
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.753.455 11.001.320 314.120.356 l
17. Gross Electrical Energy Generated (MWH) 939,333 3 764.589 101.036.520 1

4:

18. Net Electrical Energy Generated (MWH) 904.392 3.622.971 96.847.316
19. Unit Service Factor 100.0 100.0 81.7
20. Unit Availability Factor 100.0 100.0 81.7 i
21. Unit Capacity Factor (Using MDC Net) 104.8 104.9 80.2 n
22. Unit Capacity Factor (Using DER Net) 100.6 100.7 73.3
23. Unit Forced Outage Rate 0.0 0.0 6.1

' 24. Shutdowns Scheduled 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):

Forecast Achieved INITIAL CRITICALITY 08/18/82 i

INITIAL ELECTRIC!TY 10/20/84 i

i COMMERCIAL OPERATION 07/01/85 I

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4 4 to GNRO-97/00038 j

DOCKET NO 50-416 DATE 05/05/97 COMPLETED BY S.D.Lin TELEPHONE (601) 437-6793.

i MONTH Aoril1997 -

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

(MWe-Net) i 1

1263 17-1265 l

2 1260 18 1267 l

3 1256 19 1243 4

4 1244 20 1249 5

1234 21 1243 j

6 1252 22 1250 7

1264 23 1261 8

1267 24 1263 9

1264 25 1264 10 1261 26 1256 11 1256 27 1250 i

12 1265 28 1259 13 1274 29 1260 14 1272 30 1247 15 1267 31 N/A 16 1262 l

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' Attachment 3 to GNRO-97A)0038 DOCKET NO.~

50-416 UNIT NAME GGNS Unit I DATE 05A)5/97 COMPLETED BY S, D. Lin ^

TELEPHONE (601)437-6793 REPORT MONT11 April 1997 No.

Date -

Type (1)

Duratum Reason Method Of lxensee Event System Code Component Cause & Conective Action To Prevent Hours (2)

Shutting Donn Report #

(4)

Code (5)

Recunence(CACA)

Reactor (3)

None

- 1 2

3 4

5 F: Forced Reason:

Method.

Exhibit G - Instructions for Preparation of ExluWt 1-Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets forIxensee Ewnt

+

B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG4)l61) -

C-Refueling 3-Automatic Scram D-Regulatory Roan;Gies 4-Continued E-Operator Training & -

5-Reducedload Licensing Examination 6 Other F-Administratin Goperational Error (Ex1 ain) d H-Other (Explain) t T

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