ML20077Q243

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Monthly Operating Rept for Jul 1991 for Gulf Nuclear Station Unit 1
ML20077Q243
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/31/1991
From: Cottle W, Daughtery L
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-91-00144, GNRO-91-144, NUDOCS 9108210133
Download: ML20077Q243 (7)
v • d • e


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ADk.gg Entergy Operations,inc.

Operations W. T. Cottle August 14, 1991 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.

20555 Attention:

Document Control Desk Subj ect:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Monthly Operating Report GNR0-91/00144 Gentlemen:

In accordance with the requirement of Technical Specification 6.9.1.10, Entergy Operations is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for July 1991 (attachment).

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

Yours truly, e o rk WTC/TKM/cg a.tachments: 1.

Operating Status 2.

Average Daily Power Level 3.

Unit Shutdowns and Power Reductions cc:

(See next page) e

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M00PJUL/SCMPFLR - 1 9108210133 910731

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August 14, 1991 GNRO-91/00144 Page 2 of 3 4

1 cc:

Mr. D. C. Hintz (w/a)

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

)

Mr. R. B. McGehee (w/a Mr. N. S. Reynolds (w/ )

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

Mr. F. W. Titus (w/a) i Mr. Stewart D. Ebneter (w/a)

Regional Administrator U.S. Nuclear Regulatory Comission i

Region II 101 Marietta St., N.W., Suite 2900

. Atlanta, Georgia 30323 Mr. L. L. Kintner, P'oject Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission i

Mail Stop 11021

'4ashington, D.C.

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M00PJUL/SCMPFLR - 2

.. to GNR0-91/00144 DOCKET NO.

50-416 DATE 7 8/07/91 COMPLETED BY L. F. Daughtery TELEPHONE (601)437-2334 OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 Notes:

2.

Reporting-Period:

July 1991 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 WhTch 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 744 5,087 59,409
12. Number of Hours Reactor Was Critical 649.5 4,762.3 46,729.1
13. Reactor Reserve Shutdown Hours 0

0 0

16,. Hours Generator On-Line 649.5 4,664.6 44,678.3

'15. Unit Reserve Shutdown Hours 0

0 0

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16. Gross Thermal Energy Generated (MWH)

L512,447 17,206,428 153,114,499

17. Gross Electrical Energy Generated (MWH) 784, lit 5,505,358 48,568,872
18. Net Electrical Energy Generated (MWH) 751,479 5,280,95B 46,422,957
19. Unit Service Factor 87.3 91.7 78.1
20. Unit Availability Factor 87.3 91.7 78.1 l
21. Unit Capacity Factor (Using MDC Net) 88.4 90.8 73.8
22. Unit Capacity Factor (Using DER Net) 80.8 83.1 66.9
23. Unit Forced Outage Rate 12.7 8.3 6.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Eac'h):

None

25. If Shut Down.At End of Report Period.

Estimated Date of Startup:

8/02/91

26. Units In Test Status (Prior to Commercial Operation).

Forecast Achieved INITIAL CRITICALITY 08/18/82 l

INITIAL ELECTRICITY 10/20/84 l

COMMERCIAL OPERATION 07/01/85 M00PJUL/SCMPFLR

_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _. to GNR0-91/00144 j

DOCKET N0.

50-416 UNIT 1

DATE 08/07/91 COMPLETED BY L. F. Daughtery i

TELEPHONE B01-437-2334

-MONTH July 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1159.5 17 1162.7 2

1159.5 18 1161.7 3

1164.5 19 1163.7 4

1165.7 20 1154.4 5

1165.7 21 1159.4 6

1160.6 22 1157.7 7

1164.7 23 1156.2 8

1163.9 24 1158.0 9

1162.4 25 1161.9 10 1160.2 26 1164.6 11 1158.2 27 1147.1 12 1157.7 28 55.2 13-1143.8 29 0

14 1157.6 30 0

15 1161.4 31 0

16 1163.3 MOOPJUL/SCMPFLR

, to GNRO-91/00144 UNIT SHUfDOWNS AND POWER REDilCTIONS DOCKET NO.

50-416

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UNIT NAME 1

DATE 08/07/91 COMPLETED BY L. F. Daughtery '

TELEPHONE 601-437-2_34 REPORT MONTH July 1991 l

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l Method of j Licensee l

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Cause & Corrective l

l No. l Date l Type JDurationi Reason l Shutting Down!

Event i System (Component l Action To l

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l (1) l Hours l

(2) l Reactor l Report #

l Code l

Code l

Prevent Recurrence j

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(3) l l

(4) l (5) l (C&CA) l I

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191-107/28/91{

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94.5 l

A l

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91-007 l

EB l

EIC l Reactor scram from Turbine l

l009 l

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l l Control Valve (TCV) fast closure l l

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l due to loss of power to the l

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l j turbine control fluid pumps (EHC l l

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l pumps). The loss of power l

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l l Division 11 LSS load shed.

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! Outage continues.

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2 3

4 Method:

Exhibit G - Instructions F: Forced Reason:

for Preparation of Data S Scheduled A-Equipment Failure 1-Manual (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Re fueling 4-Continued File (NUREG-0161) l i

D-Regulatory Restriction 5-Reduced load E-Operator Training &

6-Other Licensing Examination 5

F-Administrative Exhibit 1-Same Source G-Operational Error (Explain)

H-Other (Explain)

M00PJUL/SCMPFLR

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i NRC SUBMITTAL CERTIFICATION FORM (Miscellaneous)

I.

Letter Number (List GNRO, GNRI, LER, Violation, etc.) July Operating Report L. F. Daughtery 08/07/91 Document Originator Date i

II. Certification: Responsible Section/ Organization Engineering Support Page/

Sentence Paragraph Number ' Number / Numbers

  1. BASIS COMMEN15 i

Attachments. 1, 2,.

Data and calculations based on GGNS Unit i

&3 l All l Switchboard Log, Rx Eng. Fuel Accounting l

l Program and STA Log entri3s.

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  1. Basis:

1)

Indicate when an action was or will be done (date) and how.

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Responsible Supv/ Supt

/ Date i

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If statement of fact list supporting document (s) i.e., UFSAR, P&ID, Procedures, etc.

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3)

May be a statemen* or conclusion which is only supported by V

engineering judgement which must be described under basis.

g6sponsibleManager Date i

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  • Signature indicated certification of the accuracy of indicated 3

portions of the document. Document may be certified with coments.

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4 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET NO.

50-416 UNIT 1

COMPLLTED BY T. K. Murray TELEPHONE T60TTT3T240T Date of Occurrence: __

July 28 1991 3

Plant Operating Condition:

Rx 1hermal Power 100%

Rx Pressure (psia) 1046.7 Rx Mode 1

Rx Power (MWE) 1220 Rx Temperatures 540'f Number of mainsteam line SRVs:

20 Number of SRVs affected by event:

11 Narrative:

On July 28, 1990, a reactor scram occurred from lurbine Control Valve fast closure due to loss of power to the turbine control fluid pumps (DIC).

The loss of power resulted from an inadveitent Division 11 LSS load shed.

The following SRV's actuated automatically once:

B21-F047A, B21-f 047C, B21-f 0470, B21-f 047G, B21-f 047H, B21-f 047L, B21-f051A, B21-f051B, B21-f0510, B21-f051f, and B21-f051K.

i M00PJVL/SCMPfLR

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