ML20133M111

Monthly Operating Rept for Dec 1996 for Grand Gulf Nuclear Station,Unit 1

ML20133M111
Person / Time
Site:	Grand Gulf
Issue date:	12/31/1996
From:	Hagan J, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-97-00005, GNRO-97-5, NUDOCS 9701220265
Download: ML20133M111 (5)

Text

.

,,,~

Entergy Operadons,Inc.

T k f{n s

I PO. Box 756

_LJ L" Port Gibson. MS 39150

/ Tel 601437 6408 Fax 601437 2705 i Joseph J. Hagan e i %ce Prr:sident l Opo<at:ons January 15, 1997 orand cuit nuaear staiion l

\

1 i U.S. Nuclear Regulatory Commission l Mall 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-97/00005 l

l Gentlemen:

In accordance with the requirement of Technical Specification 5.6.4, Entergy Operations is providing the l Monthly Operating Report for Grand Gulf Nuclear Station Unit i for December 1996.

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

Yours truly, mrr JJH/CWG l attachments: 1. Operating Status

2. Average Daily Power Level ,

3. Unit Shutdown and Power Reductions l

cc: (See Next Page)

)

220042 '

g y Q' 9701220265 961231 PDR ADOCK 05000416 R PDR,

January 15, 1997 GNRO-97/00005 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. Callan (w/a)

Regional Administrator U S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Ariington, TX 76011 l

Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 l

i

{

l 6

i

Attachment 1 to GNRO-97/00005 DOCKET NO 50-416 DATE 01/14/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 OPERATING STATUS

1. Unit Name: GGNS UNIT 1

2. Reporting Period: December 1996

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): 1228 MWE

7. Maximum Dependable Capacity (Net MWe): 1179 MWE l 8. If changes occur in Capacity Ratings (Items 3 l through 7) Since Last Report. Give Reason:

l

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

11. Hours in Reporting Period 744 8.784 ,_106.960

12. Number of Hours Reactor was Critical 744.0 7.788.0 87.979.0

13. Reactor Reserve Shutdown Hours 0 0 0 l 14. Hours Generator On-Une 733.6 7.698.4 84.876.9_ _

15. Unit Reserve Shutdown F.J' irs 0 0 0

16. Gross Thermal Energy Generated (MWH) 2.539.126 28.885.504 303.119.036

17. Gross Electrical Energy Generated (MWH) 860.729 9.602.740 97.271.931

18. Net Electrical Energy Generated (MWH) 826.736 9.224.700 93.224.345

19. Unit Service Factor 98.6 87.6 81.1

20. Unit Availability Factor 98 1 87.6 81.1

21. Unit Capacity Factor (Using MDC Net) 94.3 89.3 79.4

22. Unit Capacity Factor (Using DER Net) 88.9 84.0 72.5

23. Unit Forced Outage Rate _,

1.4 3.9 6.3

24. Shutdowns Scheduled Over Next 6 Months (Type, t., : . 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 CRITICALITY 08/18/82 INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85

j .

t Attachment 2 to GNRO-97/00005 DOCKET NO 50-416 DATE 01/14/97 COMPLETED BY S. D. Lin TELEPHONE (601) 437-6793 MONTH December 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 181 17 1280 2 123 18 1283 3 297 19 1285 I i286 4 571 20 l

5 769 21 1247 6 1192 22 1262 7 1048 23 1253 8 1253 24 1275 9 1264 25 1283 10 1255 26 1271 11 1233 27 1254 12 1241 28 1246 13 1254 29 1252 14 1256 30 1253 15 1254 31 1256 16 1271

F Attachment 3 to i ARO-97/00005 l UNIT SlaUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 50-416 UNIT NAhlE GGNS Unit l' DATE 01/14/97 COhlPLETt.O 3Y S. D. Lin "ELEPHONE (60l)437-6793 REPORT h1ONT11 December 19%

No. Date TypefIt Dur.: tion Reason l Method Of Licensee Ewnt Sptem Code Component Cause & Corrective Action To Prevent llours (2)

• Shutting Doni Report # (4) Code (5) Recurrence (CACA) l Reactor (3) 964)07 12/02/96 I- 10.4 A 6 N/A N/A l4279 Core thermal power reonced to approximately 15% to trip turbine for i

repairing crack on stub tube for INI1FX301 (isolation valve for an IIP Turbine Ist-stage pressi e transmitter) 1 2 3 4 5 F: Forced Reason: Method: Exhibit G - Instmetions for Preparation of Exhibit 1 - Same Source S: Scheduled A-Equipment Failure (Explain) 1-Manual Data Entry Sheets for Licensee Ewnt B-Maintenance or Test 2-Manual Scram Report (LER) File (NUREG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator T sining & 5-Reduced load Licensing Examination 6-Other F-Administrative G-Operational Error (Explain)

II-Other (Explain)

!