ML20057F927
| ML20057F927 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| 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
.--
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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