ML20215D874
| ML20215D874 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/31/1986 |
| From: | Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8610140339 | |
| Download: ML20215D874 (8) | |
Text
1.*
AVERAGE DAILY POWER LEVEL-(MWe-Net)
DOCKET NO.
50-316 UNIT TWO DATE 8/5/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH JULY 86 AVERAGE DAILY AVERAGE DAILY DAY
_ POWER LEVEL DAY POWER LEVEL 1
0 17 470 2
0 18 234 3
0 19 0-4 0
20-138 5
0 21 651 6
0 22 714 7
0 23 860 8
0 24 917 9
0 25 900 10 0
26 79?
11 142 27 828 12 227 28 810 13 229 29 833 14 384 30 844 15 401 31 823 16 409
2.n24
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N.R.C. OPERATING DATA REPORT DOCKET NO.
50-316 DATE 8/5/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D.
C.
Cook Unit 2
- 2. Reporting Period JULY 86-l notes l
- 3. Licensed Thermal Power (MWt) 3411 l l
4.
Name Plate Rating (Gross MWe) 1133 l l
S. Design Electrical Rating (Net MWe) 1100 l l
l
- 6. Maximum Dependable Capacity (GROSS MWe) 1100 l
- 7. Maximum Dependable Capacity (Net MWe) 1060 -----------------------
8.
If Changes Occur in Capacity Ratings (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:
This Mo.
Yr. to Date Cumm.
- 11. Hours in Reporting Period 744.0 5087.0 75215.0
- 12. No. of Hrs. Reactor Was Critical 534.9 1887.5 50916.3
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on Line 444.2 1716.7 49570.3
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Therm. Energy Gen. (MWH) 980980 4385577 155656187
- 17. Gross Elect. Energy Gen. (MWH) 294480 1392260 51078850
- 18. Net Elect. Energy Gen. (MWH) 278587 1332059 49233427
- 19. Unit Service Factor 59.7 33.7 68.1
- 20. Unit Availability Factor 59.7 33.7 68.1
- 21. Unit Capacity Factor (MDC Net) 35.3 24.7 63.8
- 22. Unit Cape;ity Factor (DER Net) 34.0 23.8 62.4
- 23. Unit Forced Outage Rate 10.3 10.0 15.6
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
s 50-316 IMM:KEI No.
IINII'SIMIIIHlWNS ANilPOWElt RElitN'llONS UNil' N AhlE D.C. Cook-Unit 2 IIATE 8-7-86 B.A. Svensson (liblPI ETEll hY RirORI higwgig July, 1986 616/465-5901 TEl.ErlHnNE PAGE 1 of 2 "t.
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ZZ ZZZZZZ The Unit was removed from service on 860228 for the scheduled Cycle 5 l
to 6 Refueling / Maintenance Outage.
The outage work has been completed and initial criticality for Cycle 6 occurred on 860707.
Low power physics testing was completed and the Unit was paralleled to the grid at 0837 hours0.00969 days <br />0.233 hours <br />0.00138 weeks <br />3.184785e-4 months <br /> on 860711 and the i
power ascension testing program was commenced.
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IMM.'KET NO. 50-316 IlNITSistiflMlWNS ANilPOWiiH NElHM'llONS D.C. Cook-Unit 2 tlNit N AME 8-7-86 IDATE B.A. Svensson l
COMFf Ell'D hy It[ FORT MON 11g July, 1986 1El.ErilONE 616/465-5901 PAGE 2 of 2
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(conti-tued)
The power ascension resting program was completed and reactor power in-creased to 80% on 860722, 90% on 860723 and~ returned to 80% on 860725.
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Dockst No.:
50-316 Unit Nam 2s
~D.C. Cook-Unit 2 Completed By:
D. A. Bruck Telephone:
(616) 465-5901.
Date:
August 8, 1986 Page:
.1 of 2 MONTHLY OPERATING ACTIVITIES - JULY, 1986 HIGHLIGHTS:
-The reporting 1 period-began with the reactor coolant system in Mcde 5.-
The reactor achieved criticality on July 7, 1986, and' L
was paralleled'to the grid on July - 11,11986, following completion
. of the low power physics testing.
Reactor power reached 69% when a trip occurred on-July 18, 1986, due to steam generator high L
level.
The Unit was' returned-to service on July 20, 1986, and-.
' reached 80% on July 22, 1986.
The reporting period ended.with the reactor at'80% rated thermal power.
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Gross electrical power generated during the month of July is 294,'480 mwh.
SUMMARY
07-04-86 At 1258, the reactor coolant system entered Mode 4.
07-05-86 At.0816, the reactor coolant system entered Mode I
- 3. 07-86' At 0157, a reactor trip occurred due to a spurious-spike on source range channel N-32.
The reactor was shutdown at the time.
At 1815, the reactor achieved criticality.
07-11-86 At 0038,'the reactor entered Mode 1.
At 0837, the generator was paralleled to-the grid.
At 1130, a power reduction was started due to arcing around the main' generator exciter.
The exciter brushes were tightened and the power decrease stopped at 22% at 1145.
At 1200, a-reactor power increase to 29%.at 3%/hr was begun, reaching 29% at 1422.
07-13-86 At 2244, a reactor power increase to 48% at 3%/hr was begun, reaching 47% at 0555 on July 14, 1986.
Docket No.:
50-316 Unit Nam 2 D.C. Cook Unit 2-Completed By:
D. A. Bruck' Telephone:
(616) 465-5901 Date:
August 5, 1986 Page:
2 of 2
SUMMARY
(Cont.)-
07-17-86 At 1414, a reactor power increase to 69% at 3%/hr was begun, reaching 69% at 2340.
07-18-86 At 0952, a reactor trip occurred due to a turbine trip which resulted from Hi-Hi level in steam generator #22.
The Hi-Hi level occurred when feedwater regulating valve FRV-220 opened fully due to a failed flow transmitter.
At 1720, reactor coolant system cooldown to Mode 4 began per Tech. Spec. 3.5.1 due to #22 accumulator being. inoperable.
At 2120, the reactor coolant system cooldown was stopped when #22 accumulator was declared operable.
07-19-86 At 0930, a reactor coolant system cooldown to Mode 4 began per Tech. Spec. 3.5.1 due to #21 accumulator being inoperable.
At 1045, the reactor coolant system was stopped when #21 accumulator was declared operable.
07-20-86 At 0847, the reactor achieved criticality.
At 1027, the reactor entered Mode 1.
At.1309, the generator was paralleled to the grid.
At 1458, a reactor power hold at 29% was started for chemistry cleanup.
At 1800, a reactor power increase to 48% was begun, reaching 48% at 2137.
At 2232, a reactor' power increase to 69% at 3%/hr was begun, reaching 68.5% at 0530 on July 21, 1986.
07-22-86 At 1421, a reactor power increase to 80% at 2.5%/hr was begun, reaching 79.5% at 2000.
i 07-23-86 At 0950, a reactor power increase to 90% at 2%/hr was begun, reaching 90% at 1640.
07-25-86 At 2126, a reactor power reduction to 80% was begun, reaching 80% at 2254.
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1 DOCKET NO.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 8-7-86 COMPLETED BY:
B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1986 M-1 Safety Valve, SV-78, on the 2-AB-2, starting air tank for Emergency Diesel Generator 2AB was leaking by.
An o-ring was replaced..The valve was tested and reinstalled.
M-2 Pressurizer spray valve was found to be leaking. Disassembled valve, replaced trim assembly, gaskets, packing, one bonnet stud and six bonnet nuts.
Stroke of valve was set and valve was tested for operability and functioned properly.-
M-3 Unit 1 Turbine Driven Auxiliary Feed Pump Trip and Throttle Valve failed to trip from control room push button. Replaced pilot valve stem assembly, upper leakoff bushing, lower leakoff bushing, yoke flange, and gaskets. Reassembled valve and tested and valve functioned properly.
M-4 Unit lE Essential Service Water Pump failed on July 26, 1986.
Pump was disassembled and found to have a broken lower pump shaft. Replaced shaft coupling, bottom shaft, bowl assembly, line shaft, lower head shaft, bearing, packing and seal / oil.
Pump was reassembled and tested and pump functioned properly.
C&I-1 BLP-141, No. 4 steam generator level indication was cycling rapidly.
Found transmitter to be defective. Replaced defective trans-mitter with new transmitter, recalibrated transmitter as per 2 THP 6030 IMP.025 and returned to service.
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Ls,,,e,,, - INDIANA & MICHIGAN ELECTRLC CAA9PANY Donald C. Cook Nuclear Plant P.O. Bas 458, Bridgman, Mchigan 49106 August 8, 1986 Director, Office Of Management Information and Program Control
~U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Pursuant to the requirements of Donald C. Cook Nuclear plant Unit 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of July, 1986 is submitted.
Sincerely, Y-l W. G. Smith, Jr.
Plant Manager WGS:ab Attachments cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen l
NRC Region III l
B. L. Jorgensen R. O. Bruggee R. C. Callen S. J. Hierzwa C. A. Erikson D. W. Paul I
D. R. Hahn i
Z.
Cordero J. J. Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department h
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