ML20082B549

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Monthly Operating Rept for June 1991 for Grand Gulf Nuclear Station Unit 1
ML20082B549
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 06/30/1991
From: Cottle W, Daughtery L
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-91-00121, GNRO-91-121, NUDOCS 9107150348
Download: ML20082B549 (7)


Text

.

e Entergy Operations. Inc.

_ g{gp Operations W. T. Cottle

.luly 10, 1991 U.S. Nuclear Regulatory Commission Mail Station PI-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-91/00121 Gentlement 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 June 1991 (attachment),

if you have any questions or require additional inforniation, please contact this office.

Yo rs truly,

/w1_

C/TKM/cg attachments: 1.

Operating Status 2.

Average Daily Power level 3.

Unit Shutdowns and Power Reductions cc:

(See next page) 910715034G 910630 PDR ADOCK 05000416 R

PDR

.g.;)'HQ061UN-1 K6 ail-

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July 10, 1991 GNRO-91/00121 Page 2 of 3 cc:

Mr. O. 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.F.W.Titus(w/a)

Mr. Stewart D. Ebneter (w/a)

Regional Administrator i

U.S. Nuclear Regulatory Commission Region 11 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 1

Mr. L. L. Kintner, Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11021

- Washington, D.C.

20555 I

l l

l-l l

t M00PJUN - 2 l

b

Attachment I to GNRO-91/00121 DOCKET NO.

50-416 DATE 07/05/91 COMPLETED BY L. f. Daughtery

_ 601)437-2I34 TELEPHONE

(

OPERATING STATUS 1.

Unit Name: GGNS UNIT 1 Notes:

2.

Reporting Period:

June 1991 3.

Licensed Thermal Power (IRT): 3833 HWT Nameplate Rating TJ72.5 MWE Design Electrical (Gross MWE): Rating (Net RWe): 1250 MWE 4.

5.

6.

Maximum Dependable Capacity (Gross HWe): IT90 MWE 7.

Maximum Dependable Capacity (Net MWe): llU MWT-8.

If Changes Occur in Capacity Ratings (Items Number 31hrough 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 4.343 58,665
12. Number of Hours Reactor Was Critical 612.4 4,112.8 46,07 G

~

'13. Reactor Reserve Shutdown Hours 0

0 0

l'

14. Hours Generator On-Line

-- 56T.T-4,015.1 44,028.8

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MrH)

T~974,761 14,693,981 150,602.052

17. Gross Electrical Energy Generated (MWH) 625,484_

4,721,266 47,784,776

18. Net Electrical Energy Generated (M(H) 596,816 4,529,479 45,671.47B

~

19. Unit Service factor 78.8 92.4 77 9 l
20. Unit Availability Factor 78.8 92.4 77.9 l
21. Unit Capacity Factor (Using MDC Net) 72.5 91.2 73.6
22. Unit Capacity Factor (Using DER Net) 66.3 83.4 66.7 1
23. Unit forced Outage Rate 2U~

7.5 6.3 l

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

None l

25. If Shut Down At End of Report Period.

Estimated Date of Startup:

NA 26.UnitsinTestStatus(PriortoCc erci 1 Operation).

I i

Forecast Achieved l

INITIAL CRITICALITY 08/18/82

~

INITIAL ELECTRIC 11Y 10/20pi4 COMMERCIAL OPERATION 677Dl/65 i

l M00PJUN/SCMPFLR

. to GNR0-91/00121 DOCKET NO.

50-416 UNIT 1

DATE D77DT/91 COMPLETED BY L. i. Daughtery TELEPHONE EDT 4TF2374 HONill June 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1156.7 17 287.9 2

1165.6 18 0

3 1163.6 19 363.6 4

1165.7 20 702.0 5

1164.7 21 747.9 6

1170.2 22 1002.7 7

1176.2 23 1136.8 8

1168.9 24 1165.4 9

1177.9 25 1155.7 10 1173.4 26 1120.0 11 840.4 27 1060.2 12 0

28 1167.1 13 0

29 1166.4 14 0

30 1153.6 15 0

31 16 209.7 M00PJUN/SCMPFLR

I to GNRO-91/00121 4

UNIT-SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416 UNIT NAME.

1 DATE 07/05/91 l

COMPLETED BY L. F. Daughtery l

TELEPHONE 601-437-2334 REPORT MONTH June 1991 i

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l l Method of l Licensee l l

l Cause & Corrective i

l No. l Date l Type [ Duration l. Reason (Shutting Downl Event l System l 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) ll (5) l (C&CA) l

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1 I

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SEAL l Replace Reactor Recirculation I

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l91-l06/11/911 S l

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B l

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i 191-l06/11/91l F

l'101.3 l

A l

3 l

91-004 l

SD l

ZC l Caused by loss of condensate /

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l feedweter flow resulting from l

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l l valve positioner failure. The l.

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j91-l06/17/91l F

ll 51.6 l

A l-3 l

91-005 l

FK l

52 l Caused by a ground fault on B l

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[ which caused a lockout on Servicel l

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l Transfonner 11. The high l

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l pressure tank and blast valve l

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l were replaced. Adjacent high l

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MOOPJUN/SCMPFLR

, to.

GNRO-91/00121 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416

. UNIT NAME I

DATE 07/05/91 COMPLETED BY L. F. Daughtery TELEPHONE 601-437-2334 REPORT MONTH June 1991 1

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions 5: Scheduled A-Equipment Failure

'l-Manual for Preparation of Data (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)

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

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

5-Other 1

Licensing Examination i

F-Administrative 5

G-Operational' Error Exhibit 1-Same' Source (Explain) j H-Other (Explair) i l

l l

l 1

MOOPJUN/SCMPFLR 6

,4 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES-DOCKET NO.

50-416 UNIT 1

COMPLETED BY I. K. Murray TELEPHONE (601) 437-2401 Date of Occurrence:

June 17, 1991 Plant Operating Condition:

Rx Thermal Power 73.7%

Rx Fressure (psig) 999 Rx Mode 1

0 Rx Power (MWE) 862 Rx Temperatures 540 F Number of mainsteam line SRVs:

20 Number of SRVs affected by event:

5 Narrative:

On June 17, 1991, a ground fault on the B Phase of Circuit Breaker J1532 caused a lock out on Service Transformer 11.

There were no automatic SRV actuations.

Thes0 SRVs were manually operated:

SRV B21-F041K actuated 3 times.

The following SRVs actuated once:

821-F0510, B21-F041E, B21-F047L and 821-F0470.

M00PJUN/SCMPFLR