ML20045A955

Monthly Operating Rept for May 1993 for Grand Gulf Nuclear Station

ML20045A955
Person / Time
Site:	Grand Gulf
Issue date:	05/31/1993
From:	Daughtery L, Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-93-00072, GNRO-93-72, NUDOCS 9306150387
Download: ML20045A955 (5)

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June 9, 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-93/00072

_ Gentlemen:

l 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 May 1993.

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

Yo s truly, s

0 - _ __

Hutchinson Vice President - Operations GGNS CRH/TMC/cg t

attachments:

1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Power Reduction ec:

(See Next Page) 1 i

1 9306150387 930531 h) p ADOCK0500g6 rg g-PDR R

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June'9, 1993 GNRO-93/00072 Page 2 of 3 i

cc:

Mr. R. H. Bernhard (w/a)

Mr.

D.

C. Hintz (w/a) r Mr. R. B. McGehee (w/a)

Mr.

N.

S.

Reynolds (w/a)

Mr.

H. L. Thomas (w/o) l

-Mr. Stewart D. Ebneter (w/a)

Regional Administrator

[

U.S. Nuclear Regulatory Commission Region II i

101 Marietta St.,

N.W.,

Suite 2900 Atlanta, Georgia 30323 Mr.

P. W.

O'Connor, Project Manager Office of nuclear Reactor Regulation U.S.

Nucleatr Regulatory Commission Mail.Stop 13H3 i

Washington, D.C.

20555 F

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h DOCKET NO 50-416 DATE 06/08/93 COMPLETED BY L.

F.

Dauchtery-TELEPHONE (601) 437-2334 OPERATING STATUS 1.

Unit Name:

GGNS UNIT 1

-2.

Reporting Period:

May 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 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 This Month Yr to Date Cumulative

11. Hours in Reporting Period 744 3,623 75.519

'12. Number of Hours Reactor was Critical 744.0 3.623.0 61,169.1

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.0 3623.0 58,836.7-

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,801.943. 13,719.038 205,959,178 17.. Gross Electrical Energy Generated (MWH) 898,390-4,461,442 65,543,274

18. Net Electrical Energy Generated (MWH) 863.413 4,290.844 62,758,768^-

19. Unit Service Factor 100.0~

100.0 80.4

-20. Unit Availability Factor 100.0 100.0 80.4-21~. Unit Capacity-Factor (Using MDC Net) 101.5 103.6 77.4 22._ Unit Capacity Factor (Using DER Net) 92.8 94.8 70.2 23._ Unit Forced Outage Rate 0

0 5.9 24._ Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of-Each):

Beain Refuelina Outaae-6 on 10/08/93 for an estimated duration of 46 days.

25. If Shut Down At End of Report Period.

Estimated Date of Startup:

26.l 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

12 to

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DOCKET NO' 50-416 l

4

~

DATE 06/08/93 COMPLETED BY L.

F.

Dauchtery TELEPHONE (601) 437-2334 1

MONTH May 1993 Day. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

'I 1

1138 17 1175

'2 1182 18 1136 3-1190 19 1185 4

1188 20 1191 l[

l 5

1179 21 1193 i

6 1177 22 1185-

'I 7

1177 23 1184 i

8 1163 24 1180 i

[

9 1175 25 1178 10 1151 26 1165

l 11 1188 27 1177 12 1122 28 1174 13-1188 29 1136

.14-1188 30 1174

)

i 15 903 31 1176 16-1059 N/A

]

1

7 7

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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO 50-416 DATE 06/08/93 COMPLETED BY L.

F.

Daughtery TELEPHONE (601) 437-2334-REPORT MONTH May 1993 No.

Date Type Duration Reason Method of Licensee System component cause &

(1)

Hours (2)

Shutting Event Code Code Corrective Down Report #

(4)

(5)

Action to Reactor Prevent (3)

Recurrence 93-05/15/93 S

32.2 B

5 NA NA NA Reactor. thermal 004 power reduced to approximately 60% for control rod sequence exchange.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G - Instructions

-S:

Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual' Scram Entry Sheets for Licensee-B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued File (NUREG-0161)

D-Regulatory Restricting 5-Reduced load E-Operator Training &

6-Other Licensing Examination 5

F-Administrative Exhibit 1-Same Source G-Operational Error (Explain)

H-Other (Explain)

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