ML17326B328
| ML17326B328 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/31/1987 |
| From: | Giles H, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC |
| References | |
| NUDOCS 8802050047 | |
| Download: ML17326B328 (12) | |
Text
REGULATOR NFQRMATIQN DISTRIBUTION 8~EM (RIDS)
ACCESSION NBR: 8802050047 DOC. DATE: 87/12/31 NOTARIZED:
NO DOCKET I FACIL:50-316 Donald C.
Cook NUclear Power Planti Unit 2i Indiana 05000316 AUTH. NAME AUTHOR AFFILIATION GILES> H.
(formerly Indiana
& Michigan Ele SMITH> W. Q.
(formerly Indiana
& Michigan Ele RECIP. NAME RECIPIENT AFFILIATION II
SUBJECT:
Monthly operating rept for Dec 1987. N/880108 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED: LTR g ENCL Q SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:
RECIPIENT ID CODE/NAME PD3-3 LA WIGGINGTQNi D CQP IES LTTR ENCL 0
0 REC IP IENT COPIES ID CODE/NAME 'TTR ENCL PD3-3 PD 5
5 INTERNAL: AEQD/DOA ARM TECH ADV NRR/DOEA/EAB NRR /P M*S/ILRB RGN3 EXTERNAL:
EQ&Q QRQH> M NRC PDR 1
1 AEOD/DSP/TPAB 2
2 NRR/DLPG/PEB 1
NR~/PEP /RPB 1
REG~LE 01 1
LPDR NSI C 1
1 1
1 1
1
~ 1 1
1 1
1 1
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 19
0
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N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-316 DATE 1/6/88 COMPLETED BY H. Giles TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D.
C.
Cook Unit 2
- 2. Reporting Period DEC87
,'notes 3.
Licensed Thermal Power (MWt) 34 1.1 4.
Name Plate Rating (Gross MWe) 1133 I
5.
Design Electrical Rating (Net MWe) 1100 6.
Maximum Dependable Capacity (GROSS MWe) 1100 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 Cumat.
11.
Hours in Reporting Period 744.0 8760.0 87648.0 12.
No. of Hrs. Reactor Was Critical 744.0 6283.1 60872.4 13.
Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14.
Hours Generator on Line 744.0 6251.6 59494.9
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.
Gross Therm.
Energy Gen.
(MWH) 1995088 16398415 182089619 17.
Gross Elect.
Energy Gen.
(MWH) 651390 4616210
.58834250 18.
Net Elect.
Energy Gen.
(MWH) 623911 4310975 56545811
- 19. Unit Service Factor 100.0 71.4 69.8
- 20. Unit Availability Factor 100.0 71.4 69.8
- 21. Unit Capacity Factor (MDC Net)
- 79. 1 46.4 62.6
- 22. Unit Capacity Factor (DER Net) 76.2 44
~ '7 61.1
- 23. Unit Forced Outage Rate 0.0 18.5 15.1 24.
Shutdowns Scheduled over Next Six Months (Type, Date,and Duration):
~qy~gnerator replacement outa'o be~in on~Aril 23 1988 for an
~ggjpgged dgrgQi~g of 225 dags.
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast INITIAL CRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved 880aoooOO7 S>~aalu PDR ADQCK 05000316 R
PDR pe'
V
~
~
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-316 UNIT TWO DATE 1/6/88 COMPLETED BY H. Giles 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 859 857 857 860 857 859 860 860 863 860 862 857 866 856 861 860 DEC87 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY POWER LEVEL 861 861 860 860 862 811 275 829 864 858 860 862 860 860 861
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Plevclil lteelirreilec 186 871222 0
.H N/A zz zzzzzz Power was reduced from 80'4 to 8X to allow an oil addition to the 821 reactor coolant pump.
Both main feedpump condensers were cleaned during this time.
Power was returne to 80'4 on-12-24-.87.
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I4Ixriucl 2 Mxuuxl Snicker.
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DOCKET NO:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE:
50-316 D.C.
Cook Unit 2 A. S. Puplis (616) 465-5901 December 2,
1987 lof 2 HIGHLIGHTS MONTHLY OPERATING ACTIVITIES -
NOVEMBER 1987 The reporting period began with the unit at 80% rated thermal power.
The unit remained at 80% power until 12-22-87, when a power reduction to 8% was initiated to add oil to the No.
21 reactor coolant pump motor.
While the unit was at the reduced power level, both main feed pump condensers were cleaned.
A reactor power increase to 80% was initiated on 12-23-87.
Reactor power was restored to 80% at 0513 on 12-24-87.
The reporting period ended with the unit at 80% power.
Gross electrical generation was 651,390 MWH for the month.
SUMMARY
12-4-87 12-6-87 Unit 2 CD Emergency Diesel Generator was inoperable from 1058 to 1147 due to a false electronic overspeed
.trip signal induced while installing temporary instrumentation for data collection.
At 0025 the West Essential Service Water (ESW) pump discharge valve (2-WM0-704), was declared inoperable due to the valve not fully stroking during its surveillance test.
The west ESW header was removed from service at 0401 the same day to troubleshoot 2-WMO-704. The valve was replaced, satisfactorily stroked, and declared operable at 1207 on 12-7-87.
During inspection of the west ESW pump discharge
- valve, internal corrosion was noticed on the pump discharge check valve (2-ESW-102W).
The valve was declared inoperable at 0950 on 12-7-87.
II a
12-22-87 12-23-87 12-24-87 12-31-87 The valve was evaluated and it's condition was determined to be acceptable, following verification of flow and seating capabilities.
The valve was returned to service, pending future repairs.
Parts are being expedited.
A power reduction to 8$ was initiated at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, to allow oil addition to the 821 Reactor Coolant Pump Notor.
Reactor Power was stabilized at 8% at 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br />.
At 1105, a power increase was initiated.
Reactor Power was restored to 805 at 0513.
At 0134 Unit 2 entered then exited Technical Specification 3.0.3 to stroke ICN-265, the South Safety Injection Pump Discharge Valve for surveillance testing.
I It n
I'
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-316 D.C.Cook-Unit No.
2 Januar 8,
1988 J.
L. St.
man 616 465-5901 1 o 1
MAJOR SAFETY-RELATED MAINTENANCE DECEMBER, 1987 2-MRV-242 (Steam Generator 84 Stop Valve Steam Cylinder Train "B" Dump Valve) was leaking by.
The plug and seat were replaced.
The valve tested satisfactorily.
I' N
),
t K
I 1
I
Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458 Bridgman, Ml 49106 616 465 5901 INIMANB SmaCIMaamr POWM Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 January 8,
1988 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 December, 1987 is submitted.
Sincerely, W.
G. Smith, Jr.
Plant Manager WGS/jd cc:
J.
E. Dolan M. P. Alexich R.
W. Jurgensen R.
C. Callen C. A. Erikson D.
W. Paul D. R.
Hahn J. J.
Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department T. R. Stephens NRC Region III B. L. Jorgensen S. L. Hall D. A. Timberlake EPRI--Nuclear Safety Analysis Center o~~
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