ML20087K001
| ML20087K001 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/31/1995 |
| From: | Htuchinson C, Lin S ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-95-00097, GNRO-95-97, NUDOCS 9508220318 | |
| Download: ML20087K001 (5) | |
Text
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.4 Ent:rgy Oper"tlin:,Inc.'
ENTERGY eo sox 7se Port Gtson.MS 39150 Tet 601437 2800 C. R. Hutchinson vce Wesn o '
OpeJ@ars Grarr3 Gun tkctar stain;n August 15, 1995
- U.S. Nuclear Regulatory Commission Mail Station P1 137 j
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-95/000 97 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 July 1995.
If you have any questions or require additional information, please contact this office.
Yours truly,
/.J CRH/TMC attachments:
1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions cc:
(See Next Page) oon4...
4~UAod 9508220318 950731 PDR ADOCK 05000416 1k i R
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August 15,;1995.'
l-GNRO-95/00097 Page 2 of 3 '
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- Mr. D. C. Hintz (wla) cc.
. Mr. R. B. McGehee (w/a) l Mr. N. S. Reynolds (w/a) -
L Mr. J. E. Tedrow (w/a).
l L
Mr. H. L Thomas (w/o)
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Mr. Stewart D. Ebneter(w/a) p
- Regional Administrator
.i U.S. Nuclear Regulatory Commission I
Region ll
- 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Ma_il Stop 13H3 -
Washington, D.C. 20555 i
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Att chment I ts GNRO-95/00097 x
DOCKET NO 50-416 DATE 08/09/95 COMPLETED BY S.D.Un TELEPHONE MQ11437 8793 OPERATING STATUS 1.
Unit Name: GGNS UNIT 1 2.
Reporting Period: July 1995 3.
Licensed Thermal Power (MWt): 3833 MWT 4.
Nemeplete Rating (Gross MWe): 1372.5 MWE 5.
Design Electrical Rating (Not 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 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 r
- 11. Hours in Reporting Period 744 5.087 94.503
- 12. Number of Hours Reactor was Critical 575.8 3.414.9 76.565.9
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 530.3 3.242.7 73.58p ')
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (MWH) 1.872.266 11.877.020 260.720.5'.i _
- 17. Gross Electrical Energy Generated (MWH) 610.441 3.865.557 83.187.056,
- 18. Net Electrical Energy Generated (MWH) 585.333 3.708.471 79.694.612
- 19. Unit Service Factor 71.3 63.8 79.8
- 20. Unit Availability Factor 71.3 63.8 79.8
- 21. Unit Capacity Factor (Using MDC Net) 68.8 63.8 77.5
- 22. Unit Capacity Factor (Using DER Net) 62.9 58.3 70.5
- 23. Unit Forced Outoge Rate 28.7 12.4 6.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End of Report Period. Estimated Date of Startup: 07/31/95 O 2258
- 26. 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 l
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~ Attichment 2 to GNRO-95/OOO97 DOCKET NO 50-416 i
2-DATE 08/09/95 COMPLETED BY S. D. Lin
[
TELEPHONE (801) 437-6793 MONTH Juiv 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
.'i 1
1218 17 14 i
2 1213 10 340 3
1035 19 1006 4
0 20 1108 5
101 21 1200 i
f 6
954 22 1199 l
7 1150 23 1200 i
8 1180 24 1200 i
I n
9 1202 25 1197
[
f 10 1201 26 1199 11 1201 27 1199 12 103 28 1198 13 0
29 1198
.l 14 0
30 598 15 0
31 0
l 16 0
-t u.~-
~ :,= to GNRO45/0009,7 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-416 i
UNIT NAME GGNS Unit 1 DATE 07/06M5 COMPLETED BY S D_ Lin TELEPHONE (601M37-6793 REPORT MONTH. Jolv l'_91_
l Type ('l[
l No.
Date Duration Reason Method Of Licensee System Code Component Cause & Corrective Action To Hours (2)
Shutting Down Event Report #
(4)
Code Prevent Recurrence (C&CA)
Reactor (5)
(3)95-007 07/U3NS F
37.7 A
3 LER #95-007 JC TRB-Reactor scram caused by a trip of Main Turbine and Reactor Feedwater Pumps resulting from an invalid reactor-water-level-high trip signal during surveillance of channel "B'.95-008 07/12/95 F
I39.9 A
3 LER #95-008 SG COMP Reactor scram caused by a Main Turbine trip on low condenser vacuum resulting from failure of an IIP condenser -
expansionjoint.
954X)9 07/30/95 F
68.4 A
3 LER #95-010 JC XCT Reactor scram caused by failure of a current transformer on 500-kV generator output breaker 15228.
I I
2 3
4 5
F: Forced Reason:
Method:
Exhibit G - Instructions for Preparation of Exhibit 1 Same Source.
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-016l)
C-Refueling
. 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator Training &
5-Reduced load Licensing Examination -
6-Other F-Administrative G-Operational Error (Explain)
H-Other(Explain) k
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