ML20057F927

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Monthly Operating Rept for Sept 1993 for Grand Gulf Nuclear Station Unit 1
ML20057F927
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/30/1993
From: Daughtery L, Hutchinson C
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-93-00124, GNRO-93-124, NUDOCS 9310190354
Download: ML20057F927 (5)


Text

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Entergy Operations,Inc.

" ENTERGY

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C. R. Hutchinson s 4 L g*

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October 14, 1993 1

l U.S.

Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.

20555 l

Attention:

Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-93/00124 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 September 1993.

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

Yours truly, d

i 2

14 CRH/TMC attachments:

1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdown and Pc'ser Reduction cc:

(See Next Page) t)\\

9nnno 9310190354~930930 PDR ADOCK 05000416 PDR b

R

Optober 14, 1993 GNRO-93/00124 Page 2 of 3 cc:

Mr. R. H. Bernhard (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 U.S.

Nuclear Regulatory Commission Region II l

101 Marietta St.,

N.W.,

Suite 2900 Atlanta, Georgia 30323 Mr.

P.

W.

O'Connor, Project Manager U.S.

Nuclear Regulatory Commission Office of Nuclear Reactor Regulation l

Mail Stop 13H3 l'

Washington, D.C.

20555 f

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Attachment I DOCKET NO 50-416 DATE 10/08/93 COMPLETED BY-L.

F.

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

Unit Name:

GGNS UNIT 1 2.

Reporting Period:

September 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 e

8.

If changes occur in. Capacity Ratings (Items 3 through 7) Since Last_ Report.

Give Resason:

N/A l

9.

Power Level To Which_ Restricted, If Any - (Net MWe) :

N/A 10.

Reasons For Restrictions,HIf Any:

N/A i

This Month Yr to Date Cumulative

{

11. Hours'in Reporting Period 720 6.551-78.447 l
12. Number of Hours Reactor was Critical 501.5 6.332.5 63.878.6
13. Reactor' Reserve Shutdown Hours 0

0 0

14. Hours Generator.On-Line 352.2 6.183.2 63.396.9
15. Unit Reserve Shutdown Hours 0

0 0

I

16. Gross Thermal Energy Generated (MWH) 1.192.869 23.276.782 215.516.922
17. Gross Electrical Energy Generated (MWH) 376.814 7.477.150 68.558.982
18. Net Electrical Energy Generated (MWH) 360,947 7.185.016 65.652.940 19.-Unit Service Factor 48.9 94.4 80 2 t

8'.7 I

20. Unit Availability Factor 48.9 94.4 J
21. Unit Capacity Factor (Using MDC Net) 43.9 96.0 77.8
22. Unit Capacity Factor (Using DER Net) 40.1 87.7 70.6

[

23._ Unit Forced Outage Rate (Type, Date, and Duration of Each):

46.8 4.8 6.1

24. Shutdowns Scheduled Over Next 6 Months
25. If Shut Down At End of Report Period.

Estimated Date of Startup: 11/07/93

[

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

t Forecast Achieved

[

L INITIAL CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION

'07/01/85 l

I 1,

.I i'

-=

' Attachment II

-l DOCKET NO 50-416 i

DATE 10/08/93 COMPLETED BY L.

F.

Dauchtery TELEPHONE (601) 437-2334 MONTH Seotember 1993 J

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

(MWe-Net) 1 1106 17 0

2 1157 18 0

i 3

1158 19 0

t 4

1031 20 0

l i

5 1169 21 0

l 6

1168 22 0

?

7 1167 23 0

f 8

1169 24 0

9 1163 25 0

10 1156 26 72 t

11 1176 27 265 I

12 1169 28 175 t

13' 737 29 0

l 14 0

30 0

r 115 0

31 N/A 16 0

N/A'

[

t h

~

.i i

._m Attaclunent ilIl UNIT SillITDOWNS AND POWER REDUCTIONS DOCKET NO 50-416

\\

UNIT NAME 1

DATE 10A17/93 COMPLETED BY L.F. Dauchterv TELEPHONE 601-437-2334 REPORT MONTil SEPTEMBER 1993 NO Date Ty,x (1)

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

Shutting Event Report # '

(4)

Code Prevent Recurrence (C&CA)

Down Reactor.

(5)

(3) l 914X)6 Owl 3/93 l'

225 6 A

3 93/X)8 UG LIS Reactor scram on high reacter water level following inadvertent actuation of high-pressure core spray syskmt Cause for actuatior suspected to be faihtre of #10 Jet Ptunp 93JK)7 09/23/93 F

SJ 2 A

1 NA SH RV Reactor shutdown from Startup Mode due to the source of high air in-IcaLage to main condenser had not been identified The source was subsequently identified to te MSR "A" Relief Vahe N1IF034A ilange leak 934)o8 0%'28/93 F/S 58 0 NC 1

93-009 AD P

Reactor shutdown fbr RFO6 tyfore t

i original schalule treause #10 Jet Pump was declared inoperable and Technical -

Specification LCO required plant shutdown..

t 1

2 3

4 5

1-F: Forced Reason:

Method:

Exhibit G -Instructions for Preparation of Exhibit 1 - Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entn Sheets for Licensee Event B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG-0161)

C-Refueling.

3-Automatic Scram D-Regulatory Restnction 4-Continued E-Operater Training &

5-Reduced load i

Licensing Examination 64)ther

' F, Awntrathe

' G-U;re.tional Error (lkplain)

Il-Other (Explain)

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