ML17328A068
| ML17328A068 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/30/1989 |
| From: | Everett T, Will Smith, Stephens T INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8907170313 | |
| Download: ML17328A068 (12) | |
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II REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8907170313
)( DOC.DATE: 897t%7"30 NOTARIZED: NO DOCKET N
FACIL:50-316 Donald O'.
Cook Nuclear Power Plant, Unit 2, Indiana 05000316 AUTH.NAME AUTHOR<AFFILIATION EVERETT,T.W.
(formerly Indiana
&, Michigan Ele SMITH,W.G.
(formerly,Indiana
.& Hjchigan Ele R
RECIP.NAME RECIPIENT,AFFILIATION I
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SUBJECT:
Monthly opera e
for'June 1989 for DC Cook Nuclear Plant Unit 2.
/,89,0710 tr.
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Indiana Michig Power Compan)
Cook Nuclear Plan P.O. Box 458 Bridgrnan, Ml 49106 616 465 5901 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington DC 20555 July 10, 1989 Gentlemen:
Pursuant to the requirements of Donald C.
Cook Nuclear Plant Unit 2 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of June, 1989, is submitted.
Sincerely, W.
G. Smith, Jr.
Plant Manager WGS/pk CC B. A. Svensson NRC Region III D. R.
Hahn EPRI Nuclear Safety Ana R.
C. Callen S. L. Hall INPO Records Center ANI Nuclear Engineering D
D. H. Williams, Jr.
M. P. Alexich J.
F. Kurgan J. J.
Markowsky D. A. Timberlake D.
W. Paul T.
O. Argenta S.
H. Steinhart B. L. Jorgensen J.
R.
Sampson D. S. Climer E.
A. Smarrella J. Krieger T. R. Stephens lysis Center epartment 70313 890630 S9071 CK 0500031+
ZSa,V rI g
N R C
OPERATING DATA REPORT DOCKET NO.
50-316 DATE 07-Jul-89 COMPLETED BYTimothy W. Everett TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D.
C.
Cook Unit 2
- 2. Reporting Period JUN 89 Inotes
- 3. Licensed Thermal Power (MWt) 3411 4.
Name Plate Rating (Gross MWe) 1133
- 5. Design Electrical Bating (Net MWe) 1100 6.
Maximum Dependable Capacity (GROSS MWe) 1100 7.
Maximum Dependable Capacity (Net, MWe) 1060
- 8. If Changes Occur in Capacity Rat,ings (Items no.
3 through 7) Since Last Report Give Reasons 9.
Power Level To Which Restricted. If Any (Net MWe) 10.
Reasons For Restrictions. If Any:
11.
Hours in Reporting Period 12.
No. of Hrs. Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 14.
Hours Generator on Line 15.
Unit, Reserve Shutdown Hours 16.
Gross Therm.
Energy Gen.
(MWH) 17.
Gross Elect. Energy Gen.
(MWH) 18, Net Elect.
Energy Gen.
(MWH) 19'nit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (MDC Net) 22.
Unit, Capacity Factor (DER Net)
- 23. Unit Forced Outage Rate 24.
Shutdowns Scheduled over Next Six This Mo.
Yr. to Date 720 '
4343.0 399.9 2258.3 0.0 0 '
393.4 2202.1 0.0 0.0 1297315 6891825 414510 2247060 400525 2167476 54.6 50.7 54.6 50.7 52.5 47.1 50.6 45.4 45.4 13.0 Months (Type, Date,and Cumm.
100775.0 65853.4 0.0 64412.1 0.0 196458202 64143280 61752141 65.4 65.4 59.2 57.7 14.5 Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved
1
AVERA DAILY POWER LEVEL (MWe-Ne DOCKET NO ~
50-316 UNIT TWO DATE 07-Jul-89 COMPLETED BYTimothy W. Everest TELEPHONE 616-465-5901 DAY 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 MONTH AVERAGE DAILY POWER LEVEL 1067 1066 1065 1067 1061 1068 1070 1063 1062 957 15 0
0 0
0 0
JUN 89 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 AVERAGE DAILY POWER LEVEL 0
0 0
0 0
0 0
61 840 1034 1044 1044 1058 1049
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH:
'JUNE, 1989 DOCKET NO.
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-316 D. C. Cook Unit g July 10, 1989 T. R. Stephens (616) 465-5901 NO.
DATE T
Y P
El D
H U
0 R
U A
R T
S I
0 N
R E
A S
0 N2 M
S D
R E
H 0
E T
U W
A H
T N
C 0
T T
D I 0
OG F
LICENSEE EVENT REPORT 5 S
C Y
0 S
D T
E4 E
M C
C 0
0 M
D P
E5 0
N E
N T
CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 195 890611 326.6 N/A SB HTEXCH The unit was shut down 890611 for containment leak inspection and lower containment ventilation unit air and waterside inspection and cleaning.
The unit returned to service 890624 with 100t RTP achieved 890625.
1 F' Forced Scheduled Reason:
A:
Equipment Failure (Explain)
B:
Maintenance or Test D:
Refueling E:
Regulatory Restriction F:
Operator Training &
I icense Examination G:
Operational Error (Explain)
H:
Other (Explain)
Method:
1:
Manual 2:
Manual Scram 3:
Other (Explain)
Exhibit G - Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit I:
Same Source
DOCKET NO:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE:
50-316 D.
C.
Cook Unit 2 T. R. Stephens (616) 465-5901 July 10, 1989 1 of 1 MONTHLY OPERATING ACTIVITIES JUNE 1989 HIGHLIGHTS The unit entered the reporting period at 100% Rated Thermal Power.
The unit was shut down June ll, 1989, for containment leak inspection and lower containment ventilation unit air and waterside inspection and cleaning.
The lower containment ventilation units were cleaned, and valve 2-SI-158-L3 was replaced.
The unit entered Mode 5 for replacement of the rod position coil stack for CBC Rod H-14.
The unit was brought critical at 1302 on June 24, 1989, with parallel to the system at 1832 on June 24, 1989.
100'-o RTP was achieved June 25, 1989.
Gross electrical generation for the month of June was 414510 MWH.
DETAILS 6/10/89 1800 6/11/89 0356 0357 0414 6/12/89 1011 2102 6/17/89 0443 6/18/89 0523 6/24/89 1302 1832 6/25/89 1622 Commenced power reduction from 100-o RTP.
Unit removed from parallel.
RCS entered Mode 2.
RCS entered Mode 3.
RCS entered Mode 4.
RCS entered Mode 5.
RCS entered Mode 4.
RCS entered Mode 3.
Reactor is critical.
Unit paralleled.
Reactor achieved 100% RTP.
DOCKET N UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE:
50-316 D.
C.
Cook Unit 2 T. R. Stephens (616) 465-5901 July 10, 1989 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JUNE 1989 Replaced bistable 1 TB-412 G/H for turbine runback/
block rod withdrawal.
Replaced bistable 2 FB-416B the low coolant flow reactor trip bistable.
Replaced valve 2-SI-158-LC.
Replaced rod position coil stack for CBC Rod H-14.
W 4