ML20094L053

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Monthly Operating Rept for Oct 1995 for GGNS Unit 1
ML20094L053
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/31/1995
From: Hutchinson C, Lin S
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-95-00123, GNRO-95-123, NUDOCS 9511200022
Download: ML20094L053 (5)


Text

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Pv1 G-osrn M3 0060 Tei U21 A37 ?&D November 13, 1995 (" ""'* h '"' *"

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i U.S. Nuclear Regulatory Commission Mall Station P1-137 Washington, D.C. 20555 I

Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNRO-95/00123 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 October 1995, if you have any questions or require additional information, please contact this office.

Yours truly, d s

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CR C attachments- 1. Operating Status

2. Average Daily Power Level
3. Unit Shutdown and Power Reductions cc: (See Next Page) i 9511200022 951031 PDR ADOCK 05000416 / V{.i R PDR /

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November 13, 1995 GNRO-95/00123 Page,2 of 3 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) l Mr. H. L. Thomas (w/o)

Mr. Leonard J. Callan (w/a) '

ReOlonal Administrator U.S. Nuclear Regulatory Commission 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 Mall Stop 13H3 Washington, D.C. 20555 M

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- Attachment 1 to GNRO-95/00123 l DOCKET NO 50-416 l DATE 11/06/95 '

COMPLETED BY S. D. Lin l

- TELEPHONE (601) 437-6793 OPERATING STATUS

1. Unit Name: GGNS UNIT 1  !
2. Reporting Period: October 1995
3. Licensed Thermal Power (MWt): .2H33 MWT
4. Nameplate Rating (Gross MWe): 1372.5 MWE
5. Design Eledrical Rating (Net MWe): 1250 MWE
6. Maximum Dependable Capacity (Gross MWe): 1??? MWE
7. Maximum Dependable Capacity (Net MWe): 1173 MWE
8. If changes occur in Capacity Ratings (items 3 through 7) Since Laat Report. Give Reason:
9. Power Level To Which Restricted, if Any (Net MWe): N/A
10. Reasons For Restridions,if Any: N/A This Month Yr to Date Cumulative 4
11. Hours in Reporting Period 745 7.296 96.172
12. Number of Hours Reactor was Critical 745.0 5.575.9 78.727.0

! 13. Reactor Reserve Shutdown Hours 0 0 0 1 14. Hours Generator On-Line 745.0 5.368.0 75.714.5

15. Unit Reserve Shutdown Hours 0 0 0 i
16. Gross Thermal Energy Generated (MWH) 2.840.215 19.798.146 268.641.641
17. Gross Electrical Energy Generated (MWH) 945.852 6.468.193 85.789.692
18. Net Electrical Energy Generated (MWH) 909.164 6.206.717 82.192.858
19. Unit Service Factor 100.0 73.6 80.2
20. Unit Availability Factor 100.0 73.6 80.2
21. Unit Capacity Factor (Using MDC Net) 104.7 73.8 78.0
22. Unit Capacity Factor (Using DER Net) 84.5 68.1 71.0
23. Unit Forced Outage Rate 0.0 9.2 6.6
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:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITIOALITY 08/18/82 INITIAL ELEC TRICITY 1~0/20/84 COMMERCIA' OPERATION 07/01/85

. Attachment 213 GNRO-95/00123

- DOCKET NO 50-416 DATE 11/06/95 COMPLETED BY S.D.Lin

.' TELEPHONE (601) 437-6793 MONTH .CLetober 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1212 17 1225 2 1214 18 1224 3 1218 19 1218 4 1219 20 1232 5 1217 21 1092 6 1230 22 1232 7 1235 23 1220 8 1234 24 1233 9 1227 25 1238 10 1223 26 1223 11 1218 27 1215 12 1215 28 1227 13 1213 29 1240 14 1212 30 1238 15 1236 31 1228 16 1228 i

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Attachement 3 to GNRO-95/00123 '

UNIT SHUTDOWNS AND POWER REDUCI10NS DOCKET NO. 50-416 UNTT NAME GGNS Unit 1 DATE 11/06/95 COMPLETED BY S. D. Ila

'IELEPHONE (60lM374793 l

REPORT MONTH October 1995

No. Date Type (1) Duration Reason Method Of Lacensee System Code Component Cause & Correctne Action To Hours (2) Shutting Event Report # (4) Code Prevent Recurrence (CACA) .

Down Reactor (5)

(3)

[None l N l j 1 2 3 4 5 l

F: Forced Reason. Method: Exhibit G - Instructions for Preparation of Exhibit 1 - Same Source ,

S: Scheduled AF 7 dpenent Failure (Explain) 1-Manual Data Entry Sheets for Licensee Event B-Mamtenance 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 I_ie*=cing Examination 6-Other F-Administrative G-Operational Error (Explain)

H-Other (Explain) i t

_ _ . _ _ _ _ ._ _ __ ___________ ______._ _ ____ ____- ___ __i__._____ _ _ _ _ _ _ _ _ _ _ _ _ _ -