ML20082B549
| ML20082B549 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| 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
.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
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t M00PJUN - 2 l
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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
1 i
l91-l06/11/911 S l
NA l
B l
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NA l
AD ll l006 l
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l l pump 'A' and 'B' seals.
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i 191-l06/11/91l F
l'101.3 l
A l
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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
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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