ML20214K040
| ML20214K040 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 05/31/1986 |
| From: | Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8608150297 | |
| Download: ML20214K040 (7) | |
Text
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i N.R.C. OPERATING DATA REPORT DOCKET NO.
50-315 DATE 6/16/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D. C. Cook Unit 1
- 2. Reporting Period MAY 86 l notes
- 3. Licensed Thermal Power (MWt) 3250 l l
- 4. Name Plate Rating (Gross MWe) 1152 l l
- 5. Design Electrical Rating (Net MWe) 1030 l l
- 6. Maximum Dependable Capacity (GROSS MWe) 1056 l l
- 7. Maximum Dependable Capacity (Net MWe) 1020 -----------------------
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:
x.,
This Mo.
Yr. to Date Cuma.}
- 11. Hours in Reporting Period 744.0 3623.0 100056.0
- 12. No. of Hrs. Reactor Was Critical 648.3 3527.3 71816.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 483.0
- 14. Hours Generator on Line 648.3 3527.3 70379.9
- 15. Unit Reserve Shutdown Hours 0.0 0.0 321.0
- 16. Gross Therm. Energy Gen. (MWH) 1901472 10341972 205337655
- 17. Gross Elect. Energy Gen. (MWH) 614850 3363840 67341380
- 18. Net Elect. Energy Gen. (MWH) 591597 3236488 64783645
- 19. Unit Service Factor 87.1 97.4 71.7
- 20. Unit Availability Factor 87.1 97.4 71.7
- 21. Unit Capacity Factor (MDC Net) 78.0 87.6 64.8
- 22. Unit Capacity Factor (DER Net) 77.2 86.7 62.4
- 23. Unit Forced Outage Rate 12.9 2.6 7.5
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
Unit shut down, expected startup 6/19/86
- 26. Units in Te..t Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8608150297 860531 ADOCKOSOOOgS DR ll
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-315 UNIT ONE DATE 6/16/86 COMPLETED BY CLIHER TELEPHONE 616-465-5901 MONTH MAY 86 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1
920 17 914 2
916 18 912 3
916 19 914 4
920 20 913 5
916 21 913 6
914 22 914 3
7 912 23 909
-('
8 911 24 911 9
912 25 914 10 913 26 910 11 918 27 878 12 916 28 4
13 916 29 0
14 914 30 0
15 917 31 0
16 915
i 50-315 IKK.KET NO.
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D.C. Cook, Unit 1 UNITSill!HHlWNS ANilPOWEN REIHirTIONS U nil N AblE 6-13-86 IIATE rublPl.ETEllliY B.A. Svensson May, 1986 HLPORT AlpN'HI TEl.ErtlONE 616/465-5901 "t.
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250 860528 F
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3 (Later)
HA INSTRU The Unit tripped from 90% RTP at 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> EDI due to a spurious main turbine backup overspeed trip l
signal. The cause,for the spurious signal is still under investigation.
During the subsequent containment inspection, several items were found which required corrective action. The RCS was brought to cold shutdown, Mode 5, and drained to half loop. The Unit remained out of service at the end of the month. Tne estimated return to service date is June 19, 1986.
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I-klanpal the Psepasanimi nf Data ll blaintenance ci Test 2 Manual Sciam.
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IL Ollies (Explain)
Dockat No.:
50-315 Unit Namot D.C. Cook Unit 1 Completed By:
A.S.
Puplis Telephone:
-(616) 465-5901 Date:
June 12, 1986 Page:
1 of 2 MONTHLY OPERATING ACTIVITIES - MAY, 1986 HIGHLIGHTS:
The reporting period began with the reactor in Mode 1 at 90%
rated thermal power.
The Unit tripped at 0020 on 5-28-86 ending a 165 day continuous run.
The reactor trip was caused by an erroneous main turbine electrical backup overspeed trip signal.
The exact cause of the trip signal is under investigation.
The reporting period ended with the Unit in Mode 5 with Reactor.
Coolant System temperature at 130*F.
Gross electrical generation for the month of May was 614,850 MWH.
SUMMARY
05-15-86 At 0305 an inadvertent Engineered Safeguards Feature (ESF) containment purge isolation signal occurred due to a high alarm on the containment area monitor, ERS 1101.
The high alarm was apparently due to a high spike, since the alarm cleared immediately.
05-27-86 At 0332, the turbine driven auxiliary feed pump was declared inoperable as a result of the turbine driven auxiliary feedwater pump failing to trip on a trip signal from the control room and subsequent attempt to close the trip and throttle valve via the motor operator.
05-28-86 At 0020 the reactor tripped from 90% power due to l
a problem in the main turbine electrical backup overspeed system.
At 0112 and 0114 an Engineered Safety Feature actuation signal was received from the lower containment air particulate monitors, ERS 1301 and ERS 1401.
The alarm / trip condition of the lower containment monitors is attributed to an increase in the reactor coolant activity following the reactor trip.
Several sources of reactor i
l coolant leakage were identified during the continment inspection.
These were corrected l
during the outage.
l At 1212 a cooldown to Mode 5 was commenced.
l At 2020 Mode 4 was entered.
l
-~
Docket No.:
50-315 Unit Names D.C. Cook Unit 1 Completed By:
A.S. Puplis Telephone:
(616) 465-5901 Date:
June 12, 1986 Page:
2 of 2 05-29-86 At 0835 Mode 5 was entered At 1240 Main Condenser vacuum was broken.
05-31-86 At 1831 the Reactor Coolant System cooldown was stopped at 130'F.
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- o DOCKET NO.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 6-14-86 COMPLETED BY B. A. Svensson PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1986 There were no major safety-related maintenance items during the month of May, 1986.
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,,,,, INDIANA & MICHIGAN ELEC1RIC COM1ANZ Donald C. Cook Nuclear Plant P.O. Box 458, Bndgman, Mchigan 49106 June 13, 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 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of May, 1986 is submitted.
Sincerely, W
d e W. G. Smith, Jr.
Plant Manager WGS:ab Attachments cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee R. C. Callen S. J. Mierzwa F. S. VanPelt, Jr.
P. D. Rennix D. R. Ifahn Z.
Cordero J. J. M.ckowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department V
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