ML20138B070
| ML20138B070 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/30/1985 |
| From: | Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8512120197 | |
| Download: ML20138B070 (7) | |
Text
,
o N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-315 DATE 10/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS 1.
Unit Name D.
C.
Cook Unit 1 2.
Reporting Period SEP 85 : notes 3.
Licensed Thermal Power (MWt) 3250 1 4.
Name Plate Rating (Gross MWe) 1152 !
1 5.
Design' Electrical Rating (Net MWe) 1030 l l
6.
Maximum Dependable Capacity (GROSS MWe) 1056 :
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 720.0 6551.0 94223.0
- 12. No. of Hrs. Reactor Was Critical O.0 1868.0 67561.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0
. 1 <4. Hours Generator on Line 0.0 1856.2 66217.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 f
321.O
- 16. Gross Therm. Energy Gen.-(MWH)
O 5418521 193588025
- 17. Gross Elect. Energy Gen. (MWH)
O
_1761840 63533730
- 18. Net-Elect. Energy Gen. (MWH) 0 1694853 61125948 1
- 19. Unit Service Factor 0.0 28.'3 71.8 f
- 20. Unit Availability Factor 0.0 28.3 71.8
- 21. Unit Capacity Factor (MDC Net)'
O.O 25,4 65.0
- 22. Unit Capacity Factor (DER Net) 0.0 25.1 62.5
- 23. Unit Forced Outage Rate 0.0 0.O' 7.2
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
s
_ _ - - _ - _ - _ _ _ - - - _ _ - _ _ _ - - = - - - - - _ _ - - - _ _ _ - - - - -
i.
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
SHUT DOWN FOR 10 YR. OUTAGE ESTIMATED ~STARTUP 9/15/85
- 26. Units in Test Status.(Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY
' COMMERCIAL OPERATION PDR ADOCK 05000315
[:' > !
e gt 8512120197 850930 7
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- i; AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-315 UNIT ONE DATE 10/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH SEP 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1
O 17 O
3' 2
0 18 0
3 t
O 19 0
4 0
20 0
5 0
21 0
6 0
22 0
s 7
0 23 0
8
/
O 24 0
9 O
25 0
10
O 26 0
11 0
27 0
12 O
28 0
13 0
29 O
14 0
30 0
15 0
31 0
16 O
0 4
i i
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i 50-315 DOCKET NO.
llNIISlHilllOWNS ANilPOWER HliDllCTIONS D.C. Cook Unit 1 IJNIT NAME DATE 10-10-85 COMPLETEllitY B. A.
Svensson a
HLPORT hlONiil September, 1985 TEl.EPilONE 616/465-5901
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Cause & Causective 1.iccusee
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Acu.m sn N..
Date g;
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livene Fy jI sE j y, g Rep <nt #
<E U lievens Hecussence t-6 246 850406 S
720 B&C 2
N.A.
ZZ ZZZZZZ The Unit was removed from service on 850406 for the scheduled ten-year ISI and Cycle VIII - IX Refueling Outage.
The outage has been extended to complete required design changes.
The estimated return to service date is October 24, 1985.
1 2
3
-1 4
1: 1:ented Heason:
Meilnad:
lintabit G - Instsuctinuis S: St heiluleil A linguiguncia 1 ailuse(l.nplain) 1 -klanual los Psepasation of Data 11 klaintenance oi Test 2 Manual Scsain.
linny Sheess fus 1.icensee C-Hefueling
.l Autunutic Stram.
liven Repiu s 11 l'lti l'ile INilHi&
D Hegulatiny Resisiction l-Othes li!xplain) 0161)
I' Opesalos I'saining & licensc i xamination 1 -Ailuunisisative 5
G Opesastonal 1:ssus liixplain)
'tisinbia I - Same Somce l'J/D)
II OthcsIlixplaini
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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Tlus report should descr$e all plant shutdowns dunng de in accordance with the taole appeanng on the report form.
report penod. In sedition. It should be the source of expian-If:stegory 4 must be used. sappiy bnei:omments.
anon of sigmncant dips m average power leveis. Each signi.
Scant redu non m power level (greater than 20% reduccan LICENSEE EVENT REPORT. Reference the applicable m average daily 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 />) reportaole occurrence pertammg to de outage or power should be noted, even cough me umt may not have been reducdon. Enter the Erst tour parts (event year. sequenna!
i shut down complete!y. For such reduchons in power level, repon numbu, occurrence cede and report type) of the Qve the duranon should be listed as :ero.the method of reducuon part designation as desenbed in item 17 of Instrucuons for should oe listed as 4 (Other), and the Cause and Correcuve Preparadon of Data Entry Sheets for Licensee Event Report Acdon to Prevent Recurrence :clumn should explain. The (LER) File (NUREG.0161). Th:s infom ation may not be Cause and Correcuve Acton to Prevent Recurrence column immediately evtdent for all suds shutdowns. of course smce should be used to provice any needed explanation to fully further mvesugation may be recuired to ascertam whether or desenbe the circumstances of the outage or power reduchon.
not a reportable occurrence was involved.) If the outage or power recuction will not result in a reportaole occurrence.
NUMBER. This column should indicate the sequential num.
the positive meication of this lack of correlation should be ber asagned to each shutdowTt orsigr.incant reducuanin power noted as not applicable WA).
for that calendar year. When a shutdown or ugmHeant power SYSTEM CODE. The system in wh:en the outage or power reduction begms m one report pened and ends m another.
reducnon ortg:nated sh'ould be noted oy me tw'o digit code of an entry should be made for born report penods to be sure all shutdowns or siamdcant power reducuens are reported.
Exhibit G. Instrucuens for Preparanon or. D2ta Entry Sheets Until a unit has achieved its first power generation, no num.
for Licensee Emt Report (LER) File (NUREG.0161).
ber should be assigned to esca entry.
Systems that do not Gt 2ny existmg code should be deugna.
ted XX. The code ZZ shou!.a ce used for dose events where DATE. ' Utis column should ad:cate de date of the start a system is not applicaole.
of esca sautdown or ugmHeant power reducdon. Report as year. month. and day. August 14.19U would be reported COMPONENT CODE. Select ce most appropnate camponent u UCS14. When a shutdown or ugruficant power reducuan from Exh: bit !. Instrucuens for Preparation of Data Entry begms m one report pened and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.01611.
be made for both report penods to be sure all shutdowns usmg the followtng entiena:
or ugnincant power reducdons are reported.
A. If a comoonent failed.use the component directlyinvolved.
TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled." respecuveiy, for each shute.own or signidcant power S.
If not a cornponent fat!ure, use the related component:
reducuan. Forced shutdowns include dose requued to be e.g.. wrong valve operated through errort list vaive 2s mitzsted by no later than the weekend followmg discovery component.
of an off. normal :endiuon. It is recogmzed that some judg.
ment is required in categoriz:ng shutdowns in th:s way. In C.
If a cham of failures occurs, the drst component to mai.
general a forced snutdown is one that would not have been function should be listed. The sequence of events. includ.
completed in de absence of the condition for which correcuve ing the other components wh2ch fail. shomd be descnbed scuan was taken.
under the Cause and Correcuve Acuan to Prevent Recur.
tence column.
DURATION. Self. explanatory. When a shutdown extends beyond the end or a report pened. count only the time to the Components that do not nt any existmg code should be de.
end of the report penod and ptek up the ensumg down ume ugnated X)CCCCX. The cole 777777 should be used for in :he fellowmg report penods. Report duranon of outages events where a component dengnat:on is not applicable.
rounded to me nearest tenth of an hout to fac:litate summanon.
CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
The sum or the total outage hours plus the hours the geners.
tot uas on line should equal the pass hours in the reportmg RENCE. Use h ch a a na tmve im m Mfy a g, g, gg,,,
ggg penod.
The column should include the spec 25c cause for each shut.
down or signadcant power reducuon and tne immediate anc REASON. Categonae hy tetter degnanon.m accordance with the taoie acpearmy on the report form. If :stegory H contemolated long term correcuve scuan taken, if scorcen.
ate. This column should also be used for a descnotion'of'tne must be used.succiy bnef comments.
maior safety-related correcuve maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reducuan mciuding an : dent 1Scation ot;
' A ' '""'*I E*'" "'""*F *"" * " E " *I 2"Y ** *I' "I'**# #'
REDUCING POWER. Categonze by number desgnanun radioaeuvity or smgle radianon exposure soertnesdy assoc:.
INote that thts differs trom the Edison Electr e Insuture 2ted with the outage which accounts for more than 10 :eteent.
iEED dednitions of " Forced Parnal Outage" and "Sene.
Of the 211owsoie annual values.
Juled Partial Outap " For these term >. EE! uses 4 saange or For long textual repons eentmue narranve on separate ; sper
-'0 MW as the breax pomt. For urpr puwer reactors. 30 MW and referen e the shutdewn or power redu uun no tnt
- s v.io imall 2 :tarvae ta manant apiananon.
narrative.
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1 Docket No.:
50-315 Unit Name:
D. C. Cook Unit 1 Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
October 3, 1985 i
Page :
1 of 1 MONTHLY OPERATING ACTIVITIES - SEPTEMBER, 1985 HIGHLIGHTS:
The unit is currently in the 10 year ISI and cycle 9 refueling outage.
There was no electrical generation in the month of September.
SUMMARY
09-01-85 At 0350, the West Residual Heat Removal Heat Exchanger was returned to service after repairing a leaking outlet cooldown isolation valve (removed from service 8-31-85 at 0042).
09-02-85 At 2258, an inadvertant Engineered Safeguard Features actuation (steamline isolation) was received due to high steam flow coincident with low steam line pressure. This was caused by standing alarms when the SSPS relays were returned to normal after surveillance testing.
09-06-85 At 1635, an Unusual Event was declared due to injured person requiring a hospital stay greater than 48 hrs (person injured on 09-05-85).
At 1720, the Unusual Event was terminated.
At 1842, an inadvertant Engineered Safeguard Features actuation resulted when switching CRID III and IV power supplies which temporarily removed the actuation blocks.
09-07-85 At 0215, an inadvertant Engineered Safeguard Features actuation occurred due to work in progress on the #11 Steam Generator flow transmitters.
At 0720, the CRID III bus voltage was lost.
At 0835, the CRID III bus was returned to service.
The reactor coolant system remained in Mode 5, Cold Shutdown, at the end of the month.
l l
1
p.
- [
DOCKET NO.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-11-85 COMPLETED BY B. A. Svensson MAJOR SAFETY-RELATED MAINTENANCE e
SEPTEMBER, 1985 M-1 A 3/4 inch crack was discovered in the weld joint where the 3/4~ inch line from 1-RH-127W (equalizing line around RHR heat exchanger outlet hand shutoff valve, RH-128W) meets the 8 inch RHR piping. 'The crack was ground out, rewelded and required NDE performed.-
C&I-l AB diesel #4 cylinder manifold temperature thermocouple on the front bank had pegged high.
Found thermocouple open. Replaced thermocouple and verified proper operation.
C&I-2 N-32 source ~ range channel spikes high and initiates "Hi Flux At Shutdown". alarms. A new low noise preamplifier was installed and the source range drawer was bonded to plant ground under RFC-12-2828.
The source range drawer was calibrated and proper operation was verified.
.C&I-3 Found No. 4 steam generator narrow range level channel, BLP-142, out of calibration. Recalibrated BLP-142.
C&I-4 Loop 1 Tave indication drifts high then back low.
Found I/I TY-412 would not calibrate.
Installed new I/I and calibrated.
C&I-5 Turbine driven auxiliary feedpump trip and throttle valve would not latch.
Found-lower coil on solenoid was burnt.
It was also discovered that'the wrong coil for the trip solenoid had been used.
I' stalled correct solenoid and verifiedLcorrect operation.
n
D"2 wouw a wcmas wcrac comur Donald C. Cook Nuclear Plant -
P.O. Box 458, Bndgman Mchgan 49106 October 12, 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 September, 1985 is submitted.
Sincerely, m
Plant Manager WGS:ab AttacFaents cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee R. C. Callen S. J. Hierzwa F. S. VanPelt, Jr.
P. D. Rennix D. R. Hahn Z.
Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department u
i