ML20136B701
| ML20136B701 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/31/1985 |
| From: | Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8511200267 | |
| Download: ML20136B701 (6) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-315 a
,Sy -
DATE 9/4/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 1
OPERATING STATUS 1;
j 1.
Unit Name D.
C.
Cook Unit 1
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2.
Reporting. Period AUG 85 Inotes 3.
Licensed Thermal Power (MWt) 3250 :
I 4.
Name Plate Rating (Gross MWe) 1152 !
5.
Design Electrical Rating (Net MWe) 1030 1 6.
Maximum Dependable Capacity (GROSS MWe) 1056 1 i
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:______________________
This Mo.
Yr. to Date Cumm.
- 11. Hours.in Reporting Period 744.0 5831.0 93503.0
- 12. No. of Hrs. Reactor Was Critical O.0 1868.0 67561.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0
- 14. Hours Generator on Line 0.0 1856.2 66217.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 321.0
- 16. Gross Therm. Energy Gen. (MWH)
O 5418521 193588025
- 17. Gross Elect. Energy Gen. (MWH) 0 1761840 63533730
- 18. Net Elect. Energy Gen. (MWH) 0 1694853 61125948
- 19. Unit Service Factor 0.0 31.8 72.4
- 20. Unit Availability Factor 0.0 31.8 72.4
- 21. Unit Capacity Factor (MDC Net) 0.0 28.5 65.5
- 22. Unit Capacity Factor (DER Net) 0.0 28.2 63.0
- 23. Unit Forced Outage Rate 0.0 0.0 7.2
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
Mode 2 expected 9/17/85
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION sd 8511200267 850831 PDR ADOCM 05000315 W
R PDR A
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6 AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-315 UNIT ONE DATE 9/4/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH AUG 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1
0 17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
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50-315 DOCKET NO.
IlNITSIRJll) OWNS ANilPOWiin plElgN TIONS UNIT NAME D.C. Cook Unit 1 DATE 9-7-85 COMPLETEll NY B. A. Svensson REPORT MONHi August, 1985 TEl.EPflONE 616/465-5901 e.
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ME sE j ;y, g Nep.ns e m' O Psevcos Hecausence t-246 850406 S
744 E&C 2
N.A.
ZZ ZZZZZZ The Unit was removed from service on l
850406 for the scheduled ten-year ISI and Cycle VIII - IX Refueling Outage. The outage has been extended to complete major required design changes. The estimated return to service date is September 18, 1985.
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UNIT SHLTDOWNS AND POWER REDUCTIONS 4
l INSTRUCTIONS Tlus report should descr:be a!! plant shutdowns during the
- n accordance with the tan le appearms on the report form.
report period. In addition,it should be the source of explan.
If category 4 must be used. supply bnef comments.
anon of sigmficant dips m average power levels. Each sipi.
I tlcant reducuon in power level (greater than 20% reduction LICENSEE EVENT REPORT z.
Reference the applicable in average dady power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportacle occurrence pertammg to the outage or power i
should be noted, even though de unit may not have been reduction. Enter the first four parts (event year, sequent:21 I
shut down complete!y. For such redactions in power level, report number, occurrence code and report type) of the Sve l
the duration should be listed as zero. the method of reduction part designation as descnbed in item 17 of Instruccons for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Enny Shats for Licensee Ewnt Repon i
Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This mformation may not be Cause and Correct:w Acnon to Prevent Recurrence column immediately evident for all sudi shutdowns.uf course, since should be used to provide any needed explanation to fully turther invesugation may be requ: red to ascertam whether ur descnbe the circumstances of the outage or power reduction, not a reportable occurrence was involved.) If the outage or power reduction will not result.n a reportable occurrence.
f NUMBER. This column should indicate the sequential num.
the posinve mdication of this lack of correlation should be i
ber assigned to each sautdown or sigmAcant reduction in power noted as not applicable (N/A).
I for th,c calendar year. When a shutdown or nentricant power SYSTEM CODE The system in whsch the outage or power reducuon begms in one report pened and ends m another.
reduction onginated sh' uld be noted or the tw'o digit eode of o
an entry should be made for both report periods to be sure 211 shutdowns or sigmdcartt power reductions are reported.
Extubit G. Instruccons for Preparanon of Das. Entry Sheets Unt:12 unit has achieved its first power generation, no num.
for Licensee Event Report (LER) File (NUREC4161).
i ber should be assagned to each entry.
Systems that do not fit sny existmg code should be deugna-ted XX. The code ZZ should be used for those events where i
DATE. T!us column should indicate the date of the start a system is not applicaole.
of each shutdown or sigmilcant power reduction. Report as year. month. and day. Aug'ast 14.19M would be reported COMPONENT CODE. Select the most apprepnate component as U0814. When a shutdown or stytficant power reduccon from Exhibit ! Instructions for Preparatton of Data E:ttr>
bepts in one report pened and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG41611.
be made for both report penods to be sure all shutdowns ussng the followtas entiens:
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or ngsricant power reductions are reported.
A. If a component faded.use the component directlyinvolved.
4 TYPE. Use "F" or S** to indicate either " Forced" or " Sche.
4 duled." respectively, for each snutdown or signiticant power B.'
If not a component fadure, use the related 'omponent.
c reduccon. Forced sautdowns laciude those required to be e.g., wrong valve operated tarough errort list nive as
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inttisted by no later than the weekend following discovery component.
of an off. normal condition. It is recopized that some judg.
l ment is required in categorizmg shutdowns In tfus way. In C. If a chasn of fadures occurs. the first component to mai.
pneral. a forced shutdown is one that would not have been function should be listed. The sequence of events. inc!ud.
j completed in the absettce of the cotiditfort for which corrective ing the other components which fail, should be descrtbed acuan was taken.
under the Cause and Correeuw Action to Prewnt P.ecur.
tence column.
DURATION. Self. explanatory. When s shutdown extends l
beyond the end of report penod, count oruy the tiras to the Components that do not tlt any existing code should be de-signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing dowet tirrte us the following resort penods. Report duranon of outages ewsts where a compostent designatiori ts not appticaole,
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ruunded to the nearest tenth of an hour to facdicate surnmanon.
CAUSE & CORRICTIVF ACTION TO PREVENT RECUR.
j l'he sum of the total outage hours plus the hours the pnera.
tot was on lme should equal the gross hours in the reportag RENCE. Use the column in a narrative fasluon to amplify or penod.
explass the circumstances of the shutdown or power recucuan.
The column should include the specinc cause (or esca shut.
- " f "gm6 cant pown reductmn and the t nmediate ama REASON. Categortze hy letter dengnation in accordance
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with the taale apoeurtrig on the report form. If category H N " """ ** * * # **
j must be used.sueply brtet eumments.
are. This column shcuid also be used for a desenption of the major safety related corrective maintenance performed dunne METHOD OF SHUTTING DOWN THE REACTOR OR the outsp or power reduction including an 'denti:1 cation of l
REDUCING - POWER. Categoner ey number despauun the cnusal path acuvity and a report of any smgle release of radioastav.8) or sm61e radiauon exposure speettkatly asses:.
INue that this differs trom the Edison E!ec:ne Insuture sted with the outage which ascounts ror more than 10 per.ent l
t EEI) derlmtions ot " Forced Parnal Outage'* and "Sene.
of the allowaaie annual values.
l
.tu;ed Parnal Outer." For these terms. eel uses 4 hange of For long textual reports sentinue narrative on sepstate paper
.'O MW as the break pinnt. For larger power reactors.30 MW
.nd referen.e the shutdown or power redu. tion IW tma
- s em small a shany to warrant esplanathat.
narrative.
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4 Docket No.:
50-315 Unit Namn D.C. Cook Unit 1 I
Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
September 6, 1985 Page:
1 of 1 l
MONTHLY OPERATING ACTIVITIES - AUGUST, 1985 i
HIGHLIGHTS:
The Unit is currently in the 10 Year ISI and Cycle 9 Refueling 3
Outage.
There was no electrical generation in the month of August.
SUMMARY
i 8-01-85 At 0838, the Unit entered Mode 5.
8-03-85 At 2339, an inadvertant safety injection was received i
on steam generator main steamline differential pressure while performing' instrument surveillance tests.
8-07-85 At 0042, an inadvertant Engineered Safeguard Features actuation (Steamline Isolation) was received due to high steam flow on Loop 3 compared with 2/4 low steam j
. pressure.
This was caused by a root valve leaking by during a steam generator hydrostatic test resulting in l
a false high steam flow signal.
8-09-85 At 1331, an inadvertant Engineered Sateguards Features actuation was received on Hi-Hi Steam' Generator level j
caused by instrument surveillance tests.
i At 1515, the Control Room Cable Vault Halon System was declared operable.
8-11-85 At 2307, an Unusual Event was declared because of an injured, contaminated man.
All required notifications were made.
8-12-85 At 0125, the Unusual Event was terminated.
i 8-18-85 At 1053, an-inadvertant Engineered Safeguard Features actuation was received due to high steam flow coinci-l dent with low steam pressure.
Standing alarms existed e
for-low stc9m pressure and one high steam flow when a
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second high steam flow signal occurred.
The reactor coolant system remained in Mode 5, Cold Shutdown, at-the end of the month.
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DOCKET NO.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 9-7-85 COMPLETED BY B. A. Svensson 4
MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1985 1
-M-1 During IS1.038, both secondary manways.on #4 steam generator were' discovered to be leaking. Gaskets were replaced per MHP 5021.002.005.
2 M-2 Replaced FMO-222, motor driven auxiliary feed pump isolation valve to #2 steam generator with a new valve. Old valve leaked by and couldn't be repaired.
New valve tested for operability.
M-3 ECR-31 and ECR-32, containment air monitor ERS-1300 isolation valves were discovered to be leaking by while performing STP.203.
Valves were disassembled and plugs, cages, seat ring and stems were replaced. Valves were re-tested under STP.203 and passed.
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INDMMA & MlCN!GAN ELECTRIC COMB 4NY yst Donald C. Cook Nuclear Plant P.O. Box 458, Bndgman. Mchgan 49106 September 7, 1985 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 August, 1985 is submitted.
Sincerely, d a_ f _ _-..
pn..
M 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. Hahn Z.
Cordero J. J. Markoweky S. R. Khalil J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department i i i
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