ML20101T156

Monthly Operating Rept for June 1992 for Grand Gulf Nuclear Station Unit 1

ML20101T156
Person / Time
Site:	Grand Gulf
Issue date:	06/30/1992
From:	Cottle W, Daughtery L ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-92-00090, GNRO-92-90, NUDOCS 9207200315
Download: ML20101T156 (6)

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July;15.11992 cae cd New h*

U.S.;NUcleer Regulatory Commission s Mail Station P1-137-

. Washington, D.C. =20555 C

,' Attention: .

Document Control' Desk "n-

Subject:

= Grand Gulf Nuclear Station--

- Unit 1

$J Docket ~No. 50-416 l" > License No.=~NPF-29 L Monthly 0perating_ Report GNR0-92/00090-

/ Gentlemen:!

A In accordance with.the requirement of Technical Specification 6.9.1.10,

.Entergy Operations:is-providing the Monthly Operating. Report for Grand H  : Gulf Nuclear Station Unit l1 for June 1992. ,

1 L.  ::

2 If you have any que_stions or require additional information, please

. ccontact:this officel Yours truly, v - - w-

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-attachments:f1. '.0perating Status.

2. Average Daily Power Level

3. Unit Shutdowns and Power Reductions-

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July 15,~ 1992 GNR0-92/00090 Page 2 of-3 cc: Mr. D. C. Hintz (w/a)

Mr. J. L. Mathis (w/a)

Mr. R. B. McGehee (w/a).

Mr. N. S. Reynolds (w/a)

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

Mr. Stewart D. Ebneter (w/a)

Regional Administrator _

U.S. Nuclear Regulatory Comission Region II 101 Marietta_St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W.- 0'Connor, Project Manager- (w/2)

Office of Nuclear Reactor Regulation U.S. Nuclear Retjulatory Comission Mail Stop 13H3 Washington, D.C. 20555

-M00PJUN/SCMPFLR 1, Attachment 1 to GNRO-92/00090 DOCKET NO. 50-416-DATE 07/10/92-COMPLETED BY ~ ,L F. Daughtery TELEPHONE (601)437-2334 OPERATING STATUS

1. ' Unit Name: GGNS UNIT 1 Notes:

2.. Reporting Period: June 1992

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): 1190 MWE

7. Maximum Dependable Capacity (Net.MWe): 1143 MWE 8 .'- If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.

Give Reasons:

N/A

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

10. Reasons For Restrictions, If Any: N/A This Month Yr to Date Cumulative 11=. Hours In Reporting Period 720 4,367 67,479

12. Number of Hours Reactor Was Critical 553.6- 2,974.0 53,171.1

13. Reactor Reserve Shutdown Hours 0 0- 0

?l4. Hours Generator On-Line 444.3 2,811.3 50,861.7

15. Unit Reserve Shutdown Hours 0 0 0 l16. Gross Thermal Energy Generated (MWH) 1,382,334 10,098,804 175,821,998

17. Gross Electrical Energy Generated (MWH) 440,425 3,226,068 55,796,178

-18. Net Electrical Energy Generated (MWH) 421,265 3,093,071 52,353 a 786

19. Unit Service Factor 61.7 64.4 7T9-

20. Unit Availability Factor 61.7 64.4 77.9

21. Unit Capacity. Factor (Using MDC Net) 51.2 62.0 74.1

22. Unit Capacity Factor-(Using DER Net) 46.8 56.7 67.2

23. Unit Forced Outage Rate 24.9 11.7 6.8

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

'25. IT 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 l

M00PJUN/SCMPFLR

-', Attachment 2 to GNR0-92/00090 4

DOCKET NO. 50-416 UNIT 1 DATE F7/10/92 ~

COMPLETED BY L. F. Daughtery TELEPHONE 601-437-2334

/

-i40 NTH June 1992 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (idWe-Net) 1 0 17 1169 2 -0 18 454 3- 0- 19 0 4 -- _- 0 20 0 5 0 21 204-6 0 22 632 7 0 23 1081 8 0 24 958 9- 22- 25 1073

10- 255 26 979 738 27 1127 12: -953 28 1175 13 :- 1072 29 1049 7 14- 1176 30 1117

~

L.15 1121 31' NA

16: 1168- NA M00PJUN/SCMPFLR--

Attachment 3 to GNRO-92/000'90'-

UNIT SHUTDOWNS AND POWER REDUCTIONS .' ~

DOCKET .40. 50-4161 UNIT NAME l' . -

DATE 07/05/92 COMPLETED BY L. F. Daughtery-TELEPHONE- 601-437-2334 REPORT MONTH June 1992

.l h L Method of Licensee l l Cause & Corrective. [

No. Date Type Duration Reason Shutting Down Event Systen. Component Action To l (1) Hours- (2) Reactor Report # Code Code Prevent Recurrence l (3) (4) l (5) (C&CA) ]

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l 92- 04/17/92 5 207.3 ! C 1 N/A N/A l N/A Continued Refueling Outage l J l004  ! ) 1 l-I ,

I H I 92- ;06/18/92 ; F 68.2 B 3 92-013 TG FLT Reactor scram due to loss of EHC l 005 l fluid pressure during maintenance l l lon CHC fluid filter.

I- 1 UNIT SHUTDOWNS AND POWER REDUCTIONS 1 2 3 4 F: Forced Reason: Method: Exhibit G .nstructions S: Scheduled A-Equipment Failure 1-Manual for. Preparation of Data (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Repcrt (LER)

C-Refueling 4-Continued File (NUREG-0161)

D-Regulatory Restriction 5-Reduced load E-Operator Training & 6-Other Licensing Examination F-Administrative 5 G-Operational Error Exhibit 1-Same Source (Explain)

H-Other (Explain)

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= MAIN STEAM SAFETY RELIEF-VALVE CHALLENGES:

50-416-

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_ DOCKET ! NO. -- ,

UNIT 1 COMPLETED BY- T. M. CARTER 4

TELEPHONE (601) 437-2401 q

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-Date of Occurrence:~ June 18, 1992

Plant' Operating Condition: ,

RxPressure-(psia)1044.7

, .Rx Thermal-Power 100%-- Rx Mode 1 J "A LRx~ Power-(MWE) 1226 Rx Temperatures 523*F-

- Number of<mainsteam line SRVs:- 20 Number o'fiSRVs _affected by event:l 11-Narrative::

e -- . On-; June 18,1992, a reactor scram occurred due to loss of EHC fluid -

pressur'e during maintenance'on EHC fluid. filter. >

ET he following SRV's-; actuated automatically once:

':B21-F0470,2B21-F047A,-B21-F0518, B21-F051A, B21-F051K, B21-F047L, '

1 iB21-F051D,-B21-F047H,-B21-F051F,'B21-F047C, and B21-F047G.

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