ML20093E621
| ML20093E621 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/30/1995 |
| From: | Hutchison C, Lin S ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-95-00115, GNRO-95-115, NUDOCS 9510170003 | |
| Download: ML20093E621 (5) | |
Text
-
g.
Ent:rgy Cper;ti:n:,Inc.
- ENTERGY eo oox 7so Port Gbson MS 39150 Tel 601437 2800 C. R. Hutc.hinson vceF%ravn C4watrre Gww1 Gut' Mdv Statm October 12, 1995 i
l 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-95/00115 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 September 1995.
Also, please note that the Maximum Dependable Capacity (Gross MWe and Net MWe) has changed due to the HP turbine upgrade.
If you have any questions or require additionalinformation, please contact this office.
You s truly, R
C attachment.
1.
Operating Status 2.
Average Daily Power Level 3.
Unit Shutdown and Power Reductions cc:
(See Next Page) l'iCG37 9510170003 950930
/
v PDR ADOCK 05000416
/
8 3
R
.PDR 1
ok October 12, 1995 GNRO-95/00115 Page 2 of 3 '
l cc:
Mr. D. C. Hintz (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. J. E. Tedrow (w/a)
Mr. H. L. Thomas (w/o)
Mr. Leonard J. Collan (w/a) -
1 Regional Administrator
- U.S. Nuclear Regulatory Commission 3
Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission a
Mail Stop 13H3 Washington, D.C. 20555
?
F fl t
I g
a
t Attachmsnt 1 to GNRO-95/00115 DOCKET NO 50-416 DATE 10/05/95 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 s
OPERATING STATUS 1.
Unit Name: GGNS UNIT 1 2.
Reporting Period: Sectember 1995 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): 1222 MWE 7.
Maximum Dependable Capacity (Net MWe): 1173 MWE 8.
If changes occur in Capacity Ratings (Items 3 through 7) Since Last Report. Give Reason: HP Turbine Uograde 9.
Power Level To Which Restricted, if Any (Net MWe):
N/A
- 10. Reasons For Rectrictions, if Any:
N/A This Month Yr to Date Cumulative
- 11. Hours in Reporting Pe riod 720 6.551 95.967
- 12. Number of Hours Reactor was Critical 678.2 4.830.9 7 7. 9 8 2.Q_,
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 668.5 4.623.0 74.969.5__
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2.416.757 16.957.931 265.801.426
- 17. Gross Electrical Energy Generated (MWH) 793.010 5.522.341 84.843.840
- 18. Net Electrical Energy Generated (MWH) 760.307 5.297.553 81.283.694
- 19. Unit Service Factor 92.8 70.6 80.0
- 20. Unit Availability Factor 92.8 70.6 80.0
- 21. Unit Capacity Factor (Using MDC Net) 90.0 70.3 77.8
- 22. Unit Capacity Factor (Using DER Net) 84.5 64.7 70.8
- 23. Unit Forced Outage Rate 7.2 10.5 6.7
- 24. Shutd, owns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICAllTY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85
4 Attachmant 2 to GNRO 95/00115 DOCKET NO 50-416 DATE 10/05/95 COMPLETED BY S.D.Un TELEPHONE (601) 437-6793' MONTH Seotember 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1200 17 1105 2
1206 18 0
3 1214 19 0
4 1217 20 291 5
1211 21 810 6
1214 22 851 7
1214 23 859 8
1209 24 1175 9
1207 25 1147 to 1223 20 1222 11 1217 27 1220 12 1213 28 1220 13-1206 29 1217 14 1203 30 1208 15 1202 31 N/A 16 1198 i
'p.
~ to GNRO-95/001 L5 UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
5(k416 UNIT NAME GGNS Unit 1 DATE 10/05/95 COMPLETED BY S. D;iin TELEPIIONE (601M37-6793 REPORT MONTil Set 3tember 1995 No.
Date Type (1)
Duration Reason Method Of Licensee System Code Component Cause & Corrective Action To IIours (2)
Shutting Down Ever.t Report #
(4)
Code Prevent Recurrence (C&CA)
Reactor (5)
(3)95-010 09/17/95 F
51.5 A
3 LER # 95-011 SJ V
Reactor scram at low reactor water level caused by failure of the pump discharge check valve to close folicwing a trip of Reactor Feed Pump Turbine "B" resulting from malfunction of pressure regulating valve PRV-4 in tube oil system. Both "B" and "A" discharge check valves uere repaired to present a similar occurrence.
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-0161)
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)
II-Other (Explain)
__ _ - _ _ = _
_-