ML20101T156
| 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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- U.S.;NUcleer Regulatory Commission Mail Station P1-137-s
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Attention:
Document Control' Desk
Subject:
= Grand Gulf Nuclear Station--
"n 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 - -
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WTC/TMC/cg
-attachments:f1. '.0perating Status.
2.
Average Daily Power Level 3.
Unit Shutdowns and Power Reductions-
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39207200315 9206301
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p 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, to GNRO-92/00090 DOCKET NO.
50-416-DATE 07/10/92-
~, F. Daughtery COMPLETED BY L
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 52,353 786 a
- 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
- ', 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--
. 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)
]
l I
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 F
68.2 B
3 92-013 TG FLT Reactor scram due to loss of EHC l
I H
I 92-
- 06/18/92 ;
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)
MOOPJUN/SCMPFLR L
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= MAIN STEAM SAFETY RELIEF-VALVE CHALLENGES:
~
DOCKET ! NO. --
50-416-UNIT 1
COMPLETED BY-T. M. CARTER TELEPHONE (601) 437-2401 q
4
-Date of Occurrence:~
June 18, 1992
~
- Plant' Operating Condition:
.Rx Thermal-Power 100%--
RxPressure-(psia)1044.7 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.
E he following SRV's-; actuated automatically once:
T
':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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