ML17331A970
| ML17331A970 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/31/1993 |
| From: | Janisse J, Reynnells R, Russo M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17331A969 | List: |
| References | |
| NUDOCS 9309220198 | |
| Download: ML17331A970 (8) | |
Text
N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-316 DATE AUGUST 6, 1993 COMPLETED BY J D Janisse TELEPHONE 616-465-5901 OPERATING STATUS
- l. Unit Name D. C.
Cook Unit 2
- 2. Reporting Period Aug 1993 notes
- 3. Licensed Thermal Power (HWt) 3411 Revision 3
4.
Name Plate Rating (Gross HWe) 1133
- 5. Design Electrical Rating (Net HWe) 1090 6.
Maximum Dependable Capacity (GROSS HWe) 1100 7.
Maximum Dependable Capacity (Net HWe) 1060
- 8. If Changes Occur in Capacity Ratings (Items no.
3 through
- 7) Since Last Report Give Reasons 9.
ower eve o
ic estricte 10.
Reasons For Restrictions. If Any:
ny et e
ll. 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.
(HWH) 17.
Gross Elect.
Energy Gen.
(HWH)
- 18. Net Elect.
Energy Gen.
(HWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (HDC Net)
- 22. Unit Capacity Factor (DER Net)
- 23. Unit Forced Outage Rate 24.
Shutdowns Scheduled over Next Six None is o.
- r. to a
e 744.0 5831.0 475.5 5562.5 0.0 0.0 443.5 5530.5 0.0 0.0 1081661 17080415 320880 5522970 304978 5327503 59.6 94.8 59.6 94.8 38.7 86.2 37.3 83.8 40.5 5.2 Months (Type, Date,and umm.
137327.0 91920.0 0.0 88846.9 0.0 274668187 89277000 85999675 65.8 65.8 60.0 58.5 15.7 Duration):
25.
ut own n
o eport erio s
ima e a e o
tartup:
26.
ni s in est atus rior to ommerc a
INITIALCRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION perat on Forcast Achieved 9309220198 930906 PDR ADOCK 05000316 i R PDR
AVERAGE DAILY POWER LEVEL (HWe-Net)
MONTH DOCKET NO.
50-316 UNIT TWO DATE SEPT 6, 1993 COMPLETED BY JD JANISSE TELEPHONE 616-465-5901 AUGUST 1993 DAY 1
2 3
5 6
7 8
9 10ll 12 13 14 15 16 AVERAGE DAILY POWER LEVEL 664 319 0
0 0
0 0
0 0
0 0
0 0
307 700 724 DAY 17 18 19 20 21 22 23 24 25 26 "27 28 29 30 31 AVERAGE DAILY POWER LEVEL 733 748 745 736 761 744 745 866 906 899 149 276 477 542 667
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: August 1993 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
PAGE 1 OF 2 D. C.
COOK UNIT 2 Sept.
9, 1993 R.
D. Reynnells (616) 465-5901 DURATION NO.
DATE TYPES'OURS METHOD OF SHUTTING DOWN REASON~
REACTOR~
LICENSEE EVENT REPORT NO.
SYSTEM CODE COMPONENT CAUSE AND CORRECTIVE ACTION CODE TO PREVENT RECURRENCE 230 930802 F
275.8 H
LER 93-07 JC DET On 930802 at 1226 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.66493e-4 months <br />, the Unit 2 reactor tripped as a result of ~
a main turbine trip, caused by a ~
spurious actuation of the turbine exhaust hood high temperature trip switches.
To prevent recurrence a temporary design change was implemented, disableing the high temperature trip function but retaining the alarm function and placing the turbine trip under administrative control.
The return to service was delayed due to a reactor vessel head penetration conoseal leak which required cooldown and partial draining of the reactor coolant system.
The unit was paralleled on 930814 at 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
1 F
S Forced Scheduled 2
Reason:
A:
Equipment Failure (Explain)
B:
Maintenance or Test C:
Refueling D:
Regulatory Restriction E:
Operator Training and License Examination F:
Administrative G:
Operational Error (Explain)
H:
Other (Explain) 3 Method:
1:
Manual 2:
Manual Scram 3:
Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 1061) 5Exhibit I:
Same Source
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: August 1993 UNZT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
PAGE 2 OF 2 D. C.
COOK UNIT 2 Sept.
9, 1993 R.
D. Reynnells (616) 465-5901 DURATION NO.
DATE TYPE HOURS METHOD OF SHUTTING DOWN REASON REACTOR LICENSEE EVENT REPORT NO.
SYSTEM CODE%
COMPONENT CODE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 231 930827 F
24.7 H
LER 93-08 JC DET On 930827 at 0502 hours0.00581 days <br />0.139 hours <br />8.300265e-4 weeks <br />1.91011e-4 months <br />, the Unit 2 reactor tripped as a result of~
a feedwater transient due to a loss of control of the east main feed pump turbine.
After maintenance activies were performed on the main feed pumps, the unit was paralleled on 930828 at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />.
1 F
S Forced Scheduled 2
Reason:
A:
Ecuipment Failure (Explain)
B:
Maintenance or Test C:
Refueling D:
Regulatory Restriction E:
Operator Training and License Examination F:
Administrative G:
Operational Error (Explain)
H:
Other (Explain) 3 Method:
1:
Manual 2:
Manual Scram 3:
Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 1061) 5Exhibit I:
Same Source
DOCKET NO.:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE:
50-316 D.C.
Cook Unit 2 R.
D. Reynnells (616) 465-5901 Sept.
9, 1993 Page 1 of 3 MONTHLY OPERATING ACTIVITIES AUGUST 1993 HIGHLIGHTS The unit entered the reporting period in Mode 1 at 70o RTP.
A reactor trip from a turbine trip occurred on August 2, 1993 at 1226 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.66493e-4 months <br />.
The turbine trip was caused by a spurious activation of the turbine exhaust hood high temperature trip.
During the containment inspection, a leak was found on a reactor vessel head penetration conoseal requiring cooldown and partial draining of the reactor coolant system to effect repairs.
The reactor was taken critical on August 12, 1993 at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />.
The unit was returned,to service on August 14, 1993 at, 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
A unit trip occurred on August, 27, 1993 at 0502 hours0.00581 days <br />0.139 hours <br />8.300265e-4 weeks <br />1.91011e-4 months <br /> initiated by an unanticipated speed decrease by the east main feed pump turbine and the resulting feedwater transient.
The reactor was taken critical on August 27, 1993 at. 2307 hours0.0267 days <br />0.641 hours <br />0.00381 weeks <br />8.778135e-4 months <br /> and the unit was returned to service at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on August 28, 1993.
The unit exited this reporting period in Mode 1 at 704 RTP.
There were no challenges to the pressurizer safety valves or power operated relief valves.
Gross Electrical generation for the month of August was 320880 MWH.
DETAILS 08-02-93 1226 Reactor trip from turbine trip.
The RCS is in Mode 3.
08-03-93 08-04-93 08-05-93 08-06-93 08-07-93 0158 1203 0523 1645 0050 0910 1604 Commenced RCS cooldown.
The RCS is in Mode 4
The RCS is in Mode 5
Commenced draining of RCS to facilitate Conoseal repair.
RCS level stabilized at 619'1".
Commenced refill of RCS from RWST.
Refill of RCS complete.
DOCKET NO.:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE 50-316 D.C.
Cook Unit 2 R.
D. Reynnells (616) 465-5901 Sept.
9, 1993 Page 2 of 3 MONTHLY OPERATING ACTIVITIES AUGUST 1993 DETAILS CONTINUED 08-09-93 08-10-93 08-12-93 08-13-93 08-14-93 08-15-93 08-23-93 08-24-93 08-27-93 08-28-93 1326 1743 1810 2222 2250 0412 0011 0117 0830 0945 1850 0415 0502 2218 2307 0303 0545 1321 2020 The RCS is in Mode 4.
The RCS is in Mode 3.
The RCS is at no-load pressure and temperature.
The reactor is in Mode 2, commenced reactor startup.
The reactor is critical.
The reactor is in Mode 1.
The main generator is paralleled to the grid, increasing reactor power.
Stabilizing reactor power at 28%.
Commenced reactor power increase.
Stabilized reactor power at 75%.
Commenced reactor power increase.
Stabilized reactor power at 854 Unit trip due to failure of the east main feed pump turbine controls.
The RCS is in Mode 3.
The reactor is in Mode 2, commenced reactor startup.
The reactor is critical.
The reactor is in Mode 1.
The main generator is paralleled to the grid, increasing reactor power.
Stabilized reactor power at 444.
Commenced reactor power increase.
DOCKET NO.:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE%
50-316 D.C.
Cook Unit 2 R.
D. Reynnells (616) 465-5901 Sept.
9, 1993 Page 3 of 3 MONTHLY OPERATING ACTIVITIES AUGUST 1993 DETAILS CONTINUED 08-28-93 08-29-93 08-3 1-93 2130 2000 2230 0200 0454 Stabilized reactor power at 53%.
Commenced reactor power increase.
Stabilized reactor power at 594.
Commenced reactor power increase.
Stabilized reactor power at 70%.
DOCKET NO:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE PAGE:
50-316 D.C.
Cook Unit 2 M. E. Russo (616) 465-5901 September 6,
1993 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE Au ust 1993 No major safety-related maintenance items are included for the month of August.