ML20115F690
| ML20115F690 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1985 |
| From: | Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8504190629 | |
| Download: ML20115F690 (8) | |
Text
-. _
l' N.R.C.
OPERATING DATA REPORT
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DOCKET NO.
50-316 l
DATE 3/1/85
. COMPLETED BY
^CLIMER
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TELEPHONE 616-465-5901' g
.. OPERATING STATUS m-
.1.-Unit Name-D.
C.
Cook Unit ~2-2.. Reporting Period Feb. 85 Inotes
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- 3. Licensed Thermal Power (MWt) 3411 1 I
,,7 4.
Name Plate Rating (Gross MWu)
'1133 I l'
,if 5.-Design Electrical Rating (Net MWe) 1100 1 I
- 6.. Maximum Dependable Capacity (GROSS MWe) 1100 I I
[
7.
Maximum Dependable Capacity (Net MWe) 1060 -----------------------
8.
If Changen.0ccur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons __________________________________________
r 9.
Power Level To Which Rentricted. If Any (Net NWe) _________________
- 10. Reasons For Restrictions. If Any ________________________________
This Mo.
Yr.'to Date
- Cuenm.
- 11. Hours in Reporting Period 672.0 1416.0 62704.0
~12.
No. of Hrs. Reactor-Was Critical 672.0 1125.0 44205.0
- 13. Reactor Reserve Shutdown Hours 0.0 0,.O 0.0
- 14. Hourn Generator on Line 672.0 1106.5 40105.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
'- ~ 16. Crosn' Therm. Energy Gen. (MWH) 2271484 3632592 136710653
- 17. Gross. Elect. Energy Gen. (MWH) 752410 1202270 44907700
- 10. Net Elect. Energy Gun. (MWH) 726930 1160593 43370327
- 19. Uriit Service Factor 100.0 70.1 71.5 i
- 00. Unit Availability Factor 100.0 78.1 71.5 J21. Unit Capacity Factor (MDC Net) 102.1 77.3 60.0
- 22. Unit Capacity Factor (DER Net) 98.3
' 74.5 66.6
- 23. Unit Forced Outage Rate 0.0 18.2 12.8
- 24. Shutdowns Schedulud over Next Gix Months (Type,Date,and Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Unite ~In~TN5t 5t3tES~lPEioE~to CoEmEEc5AI~0 pee 3tioEIt
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Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l
I e
i I w+
W i
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' AVERAGE DAILY POWER LEVEL (MWe-Net) i
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DOCKET NO.
50-316 UNIT TWO DATE.
3/1/G5 COMPLETED BY CLIMER TELEPHONE 616-465-5901
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MONTH Feb. 95 AVERAGE DAILY AVERAGE DAILY
~ ' DAY POWER LEVEL DAY POWER LEVEL 1
1090 17 1039 2
1092 18 1093 3
1097 19 1064 4
1094 20 1079 5
1085 21 1003 6
1096 22 1002 7
1097 23 G75 0
1092 24 1037 9
1095 25 1089 l
10 1096 26 1070 11 1093 27 1096 12 1002 20 1090 l
13 1095 29 O
l 14 1090 30 0
l 15 1007 31 0
l 16 1091 l
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50-316 530CKET NO.
UNIIS8MIIBM)WNS AND POWEM NElHNTN)NS UMT NAME D.C. Cook Unit 2
- 3) ATE 3-9-85 COMPLETED Ny B.A. Svensson February, 1985 616/465-5901 REPORT MONDI TELEPilONE e.
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)E; Iiccusee 5-e, Cause & Cossective Acts.wi sia N.s.
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- mO 8-6 159 850223' F
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4 N.A.
HH HTEXCH Reactor power was reduced to 55% to permit removing the East main feed pump from service to check the F-P Turbine Condenser for tube leaks.
One leaking tube was plugged.
Re-actor power was returned to 100% on 850224.
I 2
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1: 1 ascsJ Mcas.m:
Mcsisud:
Entnias G-Insanecti uis S: St cJedcJ A l'igusenics.: 1:aduse (l;mgdaint i Manual for hepasaliana of Data 3 Mainsenance or Tess 2 Manual Scsani.
Esissy Slieces fin liensee C-Refueling 1 Autuen.alic &saan.
Evens Reguut il l'RII ile INilHIG D Regulasiuy Restsicii no
-8 (hises (E xplaint Ultill I-Opcianos Isanning & Ikcuse I:nansinatense I: Adnasuisesasive 5
liledne I - Sanic S.nuce G Opesasuissal I.:s..: llisplaisil 08/11)
II Otlics elini aint d
m
O UNIT SHUTDOWNS AND POWER REDUCTIONS '
INSTRUCTIONS This report should desenbe all plant shutdowns durmg te in accordance with the tai:le appearms on the report form.
report penod. In addition. it should be the source of explan.
If category 4 must be used. supply brief c:mments.
suon of significant dips m average power levels. Each signi, ficant reducuon in power level (greater than 2F, reduction LICENSEE EVENT REPORT m.
Reference the applicable in average daily power level for me preceding 24 hnurs) reportsele occurrence pertsmmg to the outage or power should be noted, even though te urut may not have been reduction. Enter the dist four parts (event year sequennal l
shut down completely. For such reducuens in power level, report number. occurrence code and report type > of the rive the dursuon should be !!sted as zero, the rnethod of reduction pan designation as descnbed m item 17 of Instruccons for should be !isted as 4 (Other), and the Cause sad Correcuve Preparanon of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG 0161). T?us information may not be Cause and Correcuve Acuan to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce snould be used to provide any needed explanation to fully further mvesugauen may be reqmred to ascertam whetast er desenbe the circumstances of the outage or power reduction.
not 2 reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.
NUMBER. This cclumn should indicate the sequential num.
th' P0""v' indlC2 tion of rats 12ck of correistion shou!d be ber assigned to each shutdown orsigraticant reducuanin power noted as not applicable (N/A).
for that c21endar year. When a shutdown or ugnincant power SYSTEM CODE. The, system in which the outage or power reduction begms in one report pened and ends m another, an entry should be.nzde for both report penods to be sure Y.
g 'I g
g 211 shutdowns or signalcant power reductions are reported.
Ex1ubit G. Instrucuans for Preparsuon of Data Entry Sheets Unt:1 a urut has achieved its first power generation, no num.
for Licensu Ennt Repon RER) Ne MEG 0161).
ber should be assigned to each entry.
Systems that do not tit sny existing code should be deugn2 ted XX. The code ZZ. should be used for those events where DATE. This column should ;ndicate the date of the start a system is not applic2 ole, of esen shutdown or ugnancant power reducuen. Report as year. month. and day. August 14.19"7 would be reported COMPONENT CODE. 54!ect the most appropnate amponent as 770814 When a shutdown or sigmilcant power reducuan from Exh: bit I. Instrucuens for Preparst:en of Data Entr) begms m one report pened and ends m another, an entry should Sheets for L!eensee Event Report (LER) File (NCREG 016!).
be ma.le for both report penods to be sure 211 shutdowns usms the following entiens:
or ugmticant power reductions are reported.
TYPE. Use "F" or "S" to indicate etther " Forced" or " Sche.
duled." respectively, for each snutdown or sigrudcant power B.
If not 2 component fadure, use the related component reducuan. Forced shutdowns include these required to be e.g.. wrong valve operated through error: list vsive as mittsted by no later than the weekend following discovny component.
of an off. normal condition. It is recognized that some judg.
ment is requsted in categonz:ng shutdowrts 'n t!us way, in C. If a cham of fadures occurs. the ntst component to mai.
general, a forced shutdown is one that *ould not have been function should be listed. The sequence of events. me'ud.
completed trt the absence of the condition for which correcuve ing the other comportents which fail. should be desenbed action was esen.
under the Cause and Correcuve Acuen to Prevent Recur.
rence column.
DURATION. Se!f. explanatory. When s thutdown extends beycnd the end of a report penod. count only the time to the Components that do. tot rit any existmg code should be de.
signated XXXXXX. The : ode Z21.22 should be used for end of the report pened and pick up the ensumg dcwn time m :he followtng report penods. Report duracon of outages events where a component designat:on is not applic2cle.
ruundeo to the nestest tenth of an hour to fac:!1 tate summation.
CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
,he sum u( the rural outage hours ;tus the hours the geners' i
RENCE. Use the cetumn in a narrattve fastuon to ampufy or tor was on 'ine snould equal the gross hours m the reportmg exclam the c:rcumstances of the shutdown orpower reduction.
period.
The column should mc!ude the specide cause for each shw wn rs@t cant pown re ucu n an t e immediate ax REASON. Categonze by :etter Jeugnanun in awardanc1r I ' ' "" * *
'"* *
- E""
- ith the taole amoearmy un the report form. If category H ste. This eoiumn should also be used for a desenotton of the must he used.suosty briet eumments.
maior safety.related :orrecute mamtenance performed Aunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reducuon me!udmg an idenuncation y i
REDUCING POWER. Categonee ev numner deutnanon
'""'21 path asunty and a re; n of sny smpe reiessa 2r rad:oastmty or smile radta: ton exacture sees:tl.2dy assos:.
INote that this differs trom the Ediwn E!estne Inst:rute ateo with the outage which accounts for more tMan 10 :e. ent IEEls derlmuens of " Forged P2ntal Outspe" and %.he.
di the 2ilowsole annual vsh.es.
Juieu P2rtra10ucave.' For these temt.14.1 uses 4 shann ut For long intual recorts eentmue narrattve an secarste racer M MW as the crea nomi. For larger ruwer resetors. N MW anu referen,e the shutdown or power redu nun no uw
- s im imall J.hange to warrant oplananon.
na rrative.
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DockGt No.:
50-316 Unit N mas D.C. Cook Unit 2 Completed By:
A. S. Puplis Telephone:
(616) 465-5901 Date:
March'11, 1985 Page:
1 of 2 MONTHLY OPERATING ACTIVITIES - FEBRUARY 1985 HIGHLIGHTS:
The reporting period began and ended with the Unit in Mode 1 at 100% rated thermal power.
Once major power reduction occurred to remove the East Main Feed Pump from service to inspect the feedpump turbine condenser for tube leaks.
The gross electrical generation for the month was 752,410 MWH.
SUMMARY
2-01-85 At 0525 started a reactor power decrease to 98% from 100% to perform a thermal power calorimetric test.
2-01-85 At 1151 started reactor power increase to 100% which was reached at 1235..
2-05-85 At 0750 started reactor power decrease to 98% from 100%
to perform surveillance tests.
2-05-85 At 0845 reactor power was further reduced to 97% from 98% due to a spuratic status alarm.
2-05-85 At 1520 started reactor power increase to 100% upon completion of the surveillance testing.
Reactor power reached 100% at 1620.
2-08-85 At 0201 ERS 2300 Lower Containment Airborne monitor inoperable due to broken pump, 2-12-85 At 0530 started reactor power decrease to 97% to perform surveillance tests.
Reactor power reached 97%
at 0650.
2-12-85 At 1437 started reactor power increase to 100% which was reached at 1620.
2-19-85 At 0519 started reactor power decrease to 97% for surveillance testing.
Power reached 97% at 0554.
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Dock;t No.:
50-316 Unit Namn P.C. Cook Unit 2 Completed By:
A. S. Puplis Telephone:
(616) 465-5901 Date:
March 11, 1985 Page:
2 of 2 2-19-85 At 2000 started reactor power increase to 100% which was achieved at 2128.
Moisture separator reheater drain valve MRV 423 was bypassed causing moisture separate reheater drains to be directed to the condenser causing a 15 megawatt load curtailment.
2-23-85 At 1050 started reactor power decrease from 100% to 55%
to remove from service the East Main Feed Pump for condenser inleakage inspection.
Reactor power reached 55% at 1215.
2-23-85 At 1645 started reactor power increase to 100% which was reached at 0110 on 2-24-85.
2-25-85 At 1840 MRV 423 was returned to service and at 2057 the moisture separator reheater was at full pressure.
2-26-85 At 0535 started reactor power decrease to 97% to conduct surveillance testing.
Reactor power reached 97% at 0555.
2-26-85 At 1457 started reactor power increase to 100% which was reached at 1539.
2-27-85 At 0930 Steam Generator 423 stop valve was declared inoperable because its associated dump valve MRV-232 was out of service for repair.
The Control room Cable Vault System remains inoperable as of 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on 4-14-83.
The backup CO System remains operable.
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DOCKET NO.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 3-9-85 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1985 M-1 No. 3 S/G stop valve dump valve MRV-232 was removed from service to correct leak by condition. New seat ring, plug, stem and gaskets were utilized to rebuild the valve. Post repair functional testing was performed to verify valve operability.
M-2 An oil leak on 2CD Emergency Diesel Generator lube oil bypass filter pump was corrected by installing a new mechan-ical shaft seal. The relief valve pressure was verified prior to returning the pump to service.
O e
i
.y. ; a; a -
G.. _mme e acuma sizersic_commax Donald C. Cook Nuclear Plant P.O. Son 468, Bndgman, Michigan 49106 I.
March 9, 1985 Director, Office Of Management Information l
and Program Control l
U. S. Nuclear Regulatory Commission l
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 February, 1985 is submitted.
Sincerely, LY./
7 W. C. Smith, r.
Plant Manager NGS:ab Attachments cc:
J. E. bolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee (NSAC)
R. C. Callen S. J. Micrzwa R. F. Kroeger B.11. Bennett
.P. D. Rennix J.11. IIennigan A.
Cordero J. J. Markovsky J. F. Stietzel PNSRC File l'
INPO Records Center l
ANI Nucicar Engineering Department I
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