ML20115H066

Monthly Operating Rept for June 1996 for GGNS

ML20115H066
Person / Time
Site:	Grand Gulf
Issue date:	06/30/1996
From:	Hutchinson C, Lin S ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-96-00081, GNRO-96-81, NUDOCS 9607220203
Download: ML20115H066 (6)

Text

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July 15, 1996 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-96/00081 Gentlemen:

In accordance with the requirement of Technical Specification S.6.4, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for June 1996.

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

You truly, e

H/ G a ments: 1. Operating Status l

2. Average Daily Power Level l

3. Unit Shutdown and Power Reductions

4. Main Steam Safety Relief Valve Challenges cc: (See Next Page) 9607220203 DR 960630 "

ADOCK 05000416 PDR

$ 5Q 1

July 15, 1996 GNRO-96/00081 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)

Mr. H. L. Thomas (w/o)

Mr. Leonard J. Callan (w/a)

Regional Admin!strator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 Mr. Jack Donohew, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555

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4 Attachment 1 to GNRO-96/00081 DOCKET NO 50-416 DATE 07/08/96 COMPLETEU BY S. D. Lin TELEPHONE (601) 437-6793 OPERATING STATUS

1. Unit Name: GGNS UNIT 1

2. - Reporting Period: June 1996 3i Licensed Thermal Power (MWt): 3833 MWT

- 4. Nameplate Rating (Gross MWe): 1372.5 MWE

5. Design Electrical Rating (Not 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:

9. Power Level To Which Restricted, if Any (Net MWe): N/A l

10. Reasons For Restrictions, if Any: N/A l l

This Month Yr to Date Cumulative i

11. Hours in Reporting Period 720 4367 102.543  !

12. Number of Hours Reactorwas Critical 668.2 4315.2 84.506.2 i

13. Reactor Reserve Shutdown Hours 0 0 0 i

14. Hours Generator On-Line 646.9 4293.9 82.192.4  !

15; Unit Reserve Shutdown Hours 0 0 0 l

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 2.386.021-784.211 16.259.479 5.424.077 290.493.011 93.093.268 j

18. Net Electrical Energy Generated (MWH) 752.700 5.212.042 92.309.057 l

19. Unit Service Factor 89.9 98.3 81.3  ;

20. Unit Availability Factor 89.9- 98.3 81.3 )

21. Unit Capacity Factor (Using MDC Net) 89.1 101,8 79.5 .l

22. Unit Capacity Factor (Using DER Net) 83.6 95.5 72.5

23. Unit Forced Outage Rate 10.2 1.7 - 6.3

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelino Outane # 8 beoinnino at 0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> on 10/19/96 for 30 days.  !

25. If Shut Down At End of Report Period. Estimated Date of Startup:  ;

26. Units in Test Status (Prior to Commercial Operation):

l i

. Forecast Achieved i

INITIAL CRITICALITY 08/18/82  :'

INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85 i

i mr ._ _ , - #

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Attachment 2 to GNRO-96/00081 DOCKET NO 50-416 DATE 07/08/96  :

COMPLETED BY S.D.Lin TELEPHONE (601) 437-6793 l

MONTH June 1996 l

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  !

(MWe-Net) (MWe-Net)  ;

t 1 1002 17 1206 2 1206 18 1211 ,

3 1220 19 1211 4 1219 20 1210 5 1214 21 1207 ,

6 581 22 1188 i 7 0 23 1209 8 0 24 1211 +

9 87 25 1208 -

10 723 26 1202 l 11 1170 27 ,

1205 12 1207 28 1209 13 1212 29 1206  ;

14 1215 30 1205 i 15 1212 31 N/A I

16 1208 i

I i

l

=

Attachment 3 to GNRO-96/00 .

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-416 UNIT NAME GGNS Unit 1 DATE 07/03/96 COMPLETED BY S. D. Lin TELEPHONE (6011437-6793 REPORT MONTH June 1996 No. Date Type (1) Duraaon Reason Method Of Licensee System Code Component Cause & Corrective Action To Hours (2) Shutting Event Report # (4) Code Prevent Recurrence (C&CA)

Down Reactor (5)

(3)96-003 06/01/96 S 0. B 6 N/A N/A N/A Reactor power reduced to approximately 75% for control rod sequence exchange.

963 M 06/06/96 F 73.1 A 2 96-004 PIS 112 1 Reactor was manually scrammed when a I spurious actuation ofboth B & F subchannels of Division II relieflogic occurred upon failiure ofa trip unit for the Safety / Relief Valves. The resulting opening ofsix S/RV's caused the Suppression Pool temperature to rise to

_ approximately 105 'F.

I 2 3 4 5 F: Forced Reason: Method: Exhibit G - Instructions for Preparation of Exhibit 1 - Same Source S: Scheduled A-Equipment Failurt (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)

H-Other (Explain)

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,$ Attachment IV to GNRO-96/00081  !

MAIN STEAM SAFETY RELIEF VALVE CHALLENGES Docket No. 50-416 l Unit 1 l

Completed By C. W. Gunn  !

Telephone (601 437-2396 l Date of Occurrence: June 6,1996 Plant Operating Condition:

RxThermalPower 100% Rx Pressure (psia) 1044.7 Rx Mode 1 i Rx Power (MWE) 1269 Rx Temperatures 540F Number of main steam line SRVs: 20 Number of SRVs affected by event: 6_

Narrative:

On June 6,1996, GGNS experienced an opening of six Main Steam Safety / Relief Valves (SRV) which resulted in an increase in suppression pool temperature. The reactor was manually scrammed by control room operators before temperature limits were reached. ,

he fo!!owing SRVs actuated:

F051D F051B F047D F047G F051A F051F l l