ML20214Q065
| ML20214Q065 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 04/30/1987 |
| From: | Dilworth S, Gucwa L GEORGIA POWER CO. |
| To: | NRC |
| References | |
| SL-2530, NUDOCS 8706040223 | |
| Download: ML20214Q065 (8) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-424 UNIT vontle i DATE
$_4_g7 COMPl.ETED BY S.C. Dilworth TELEPHONE (404)7f4_sii4, ex 337o OPERATING STATUS GROSS HOURS IN REPORTING PERIOD:
719 1.
REPORTING PERIOD:
April 1987 3411 CURRENTLY AUTHORIZED POWER LEVEL (MWt):
2.
MAX. DEPMD. CAPACITY (MWe-Net):
1069 7
DESIGN ELECTRICAL RATING (MWe-Net):
1:01 (MWe-Net):
870 POWER LEVEL TO WHICH RESTRICTED (IF ANY) 3.
1%
Plant in Startup/ Power Ascension TestYR TO" HATE CUMUI.ATIVE REASONS FOR RESTRICTION (IF ANY):
THIS MOffrH 4.
926.4 976.4 5 4 6. 9 ____
NIRIBER OF HOURS REACTOR WAS CRITICAL 5.
N/A o
o REACTOR RESERVE SHUTDOWN HOURS 6.
464.1 519.1 519.1 7.
HOURS GENERATOR ON LINE N/A O
O UNIT RESERVE SHUTDOWN HOURS 8.
797,491.7 866_ys7_y 866,257.7 CROSS THERMAL ENERGY GENERATED (MWH) 9.
220,823 227.110 2&u o CROSS ELECTRICAL ENERGY GENERATED (HWH) 10.
184,233
.L8!bri i 184.131 NET El.ECTRICAI. ENERGY GENERATED (HWH)
I1.
l 1
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8706040223 870430 i
PDR ADOCK 05000424 PDR REVISION 1 R
OPERATING DATA REPORT (. cont inucil)
THIS HONTH YR TO DATE CUHULATIVE l
73.3 73.3 76.0 l
12.
REACTOR SERVICR FACTOR 76.0 73.3 73.3 REACTOR AVAILABILITY FACTOR 13.
64.5 62.9 62.9 14.
UNIT SERVICE FACTOR 62.9 62.9 64.5 UNIT AVAILABILITY FACTOR 15.
21.94
- > 3. 94
,, _ y f, UNIT CAPACITY FACTOR (Using HDC) 16.
23.24 23.24 y,,j3 UNIT CAPACITY FACTOR (Using Design HWe) 17.
32.82 30,4i
- 3g_z, UNIT FORCED OUTAGE RATE 18.
SHUTDOWNS SCHEDULE OVER NEXT 6 HONTH 19.
(TYPE, DATE, AND DURATION OF EACH):
N/A 05/01/87 ESTlHATED DATE OF STARTUP:
IF SHUTDOWN AT END OF REPORT PERIOD, 20.
UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
21.
FORECAST ACHIEVED 3/9/87 1/9/87 INITIAL CRITICALITY 3/14/87__
3/27/87 INITIAL ELECTRICITY 6/01/87_
COMMERCIAL OPERATION REVISION 1
o LINIT StillTDOWNS AND l'OWER REDUCTIONS DOCKE r NO. 50-424 REl' ORT MONTil April 1987 UNil NAME Vontle i DATE S-4-87 COMi'I.I.TED BY S. C. DiIwortb TEl.El*llONE ( 404 ) 7 24-81 ; i, ext. 1870 Method of Licensee Systeg Component Cause & Corr.
I y
No.
Date Type Duration Reason Shutting Event Code Code Action to 3
(Moura)
Down Report (lf Prevent Reactor ()
Applicable)
Recurrence
{
i 1
4-5 F
68.6 A
3 87-012 El.
GEN See Ailili t iona l 2
4-8 S
14.6 B
1 N/A ZZ ZZZZZZ Sheets 3
4-10 F
13.5 A
3 SJ 1.CV 6
4 4-11 F
94.4 A
3 SJ 1.CV g
5 4-24 S
11.3 H
I N/A ZZ ZZZZZZ 6
4-27 F
18.3 A
5 N/A TA XXXXXX 7
4-29 F
33.9 A
3 ZZ ZZZZZZ 3
4 I
2 Method:
IEEE 805-1983 F: Forced Reason:
S: Scheduled A-Equipment Failure (Explain) 1-Manual R-Maintenance of Test 2-Manual Scram 5
C-Refueling 3-Automatic Scram IEEE 803A-1983 4-Continuations D-Regulatory RestrActton E-Operator Training & Lic. Exam.
5-Load Reduction Attachment yes X no F-Administrative 9-Other (Explain)
Number of pages _2 G-Operational Error (Explain)
H-Other (Explain) 1.ER number to be assignett REVISION 1
~
UNI! SHUIDOWNS & POWER REDUCTIONS ( Continued )
A - Cause / B - Corrective Action To Prevent Recurrence
_# _1 A.
Main Generator Fault caused Generator / Turbine Trip and Subsequent Secondary Oscillations.
Ground Relay was tripped.
l B.
Discrepancy Card (DC# l-87-1065) was initiated on Generator to correct Generator Fault. A time delay relay has been put into the circuitry for the Generator field ground relay to avoid tripping of this relay on a spurious fault indication.
i
- 2 A.
Manual Shutdown Test using the remote shutdown panel. This was part of Start-up Test Program procedure 1-600-08.
B.
N/A - due to Start-up Test.
- 3 A.
Reactor trip due to steam generator lo-lo level. The level change was due to a malfunction of a check valve on the main feedwater pump "A" discharge line and the malfunction of a motor operated valve on the discharge of the MFW pump "A".
B.
Corrective actions taken were to adjust the packing of the MFW pump "A" discharge MOV and to replace the hinge pin for the disc on the check valve.
- 4 A.
Reactor trip due to steam generator #1 low-low level trip. Trip was caused by a controller for MFRV #2 being wired incorrectly.
Corrective action was taken to reconfigure MFRV #2 consistent with B.
the other MFRVs.
$1 Reactor Reduction in power to 20%, generator off line tu repair A.
EHC leak.
i B.
EHC leak was repaired and tested.
1$
Turbine Trip on high vibration. Rx Power was reduced to 20%.
A.
B.
EHC repairs were initiated.
E-3a Fr. VISION 1
UNIT SHUTDOWNS & P0'n'ER REDUCTIONS ( Continued )
S A.
Rx Trip on OTAT and OPAT.
Pressurizer high pressure and pressurizer low pressure bistables tripped.
Replaced a defective card in the 7300 panel.
B.
)
E-3b REVISION 1
l AVEPAGE DA!'.Y '; NIT POWER LEVEL DOCKET NO.
50-424 UNIT NO.
Vogtle 1
{
DATE 5-4-87 l
COMPLETED BY s.c. Dilworth TELEPHONE (404) 724-8114, i
ext. 3870 MONTH April 1987 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Nec) i 1
248 17 409 2
241 18 421 3
253 19 423 4
287 20 427 4
5 121 21 441 6
0 22 701 7
0 23 706 8
0 24 146 9
131 25 ss6 l
10 78 26 632 F
11 o
27 217 i
12 0
28 507 1
4 13 0
29 423 4
14 0
30 0
15 270 31 N/A 16 410 i
a E-4 REVISION 1 i
- l i
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0 Georgia Power Company 333 Piedmont Avenue
]
Atlanta, Georgia 30308 Teiephone 404 526-6526 Maiiing Address:
I Post Office Box 4545 Atlanta, Georgia 30302 b
I Georgia Power L. T. Gucws tre souf>em eectrc systcvri Manager Nue: ear Safety and L! censing l
SL-2530 0303m X7GJ17-V510 May 22, 1987 Director, Office of Resource Management U. S. Nuclear Regulatory Commission Hashington, D.C.
20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REVISION TO MONTHLY OPERATING REPORT I
Gentlemen:
i Enclosed is a revised Monthly Operating Report for Plant Vogtle Unit I for April,1987.
The revised report supercedes the report provided by our letter SL-2489 dated May 7,
1987.
The report submitted by the aforementioned letter failed to account for the change to Daylight Savings Time.
As a result, we have found it necessary to revise certain of the data.
Corrected data is denoted by vertical lines drawn in the i
margins.
Sincerely, fM e-s i
j-L. T. Gucwa JAE/1m
Enclosure:
1.
Operating Data Report 2.
Unit Shutdowns and Power Reductions 3.
Average Daily Unit Power Level c:
(see next page) 1
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Georgia Power 1 Director, Office of Resource Management May 22, 1987 Page Two c: Gggraia Power ComDany Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D' Amico Mr. C. H. Hayes GO-NORMS Southern Comoany Services Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridge Mr. B. H. Churchill, Attorney-at-Law TroulmLn,_ Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-law U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle Gecraians Acainst Nuclear Energy Mr. D. Feig Ms. C. Stangler 0;33m 700775