ML20081M434

Monthly Operating Rept for Sept 1983

ML20081M434
Person / Time
Site:	Cook
Issue date:	09/30/1983
From:	Gillett W, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8311170255
Download: ML20081M434 (8)

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a CPERA OIC DATA R.EPORT

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DCC'*I~ NO. 5 0- 315 DATI 1 n 8 3 Coat?t2 IO LY t.7 m

e'4 1 l e t-s TILI?HCNZ 616-465-5901 CPI?x-'NG 5 ATUS Nor:s g, Ugg N2cte:

Donald C.

Cook 1

1 Report:n; ?s:fod:

sentember 1983 3250 3.1.:c== sed The--! Power (5tW: :

1152'

4. N2=esla:: ?.2:in;(Csor.s 3:We):

1030

5. Desiy= E==:i=1 R::in;(Ne:51We):

4. 3'-

m==: Depend.:ble Gy:ci:/ (Cross 51We):

'ncc 1n9m T. Sfaxi- - Dep==d:h!= t -- :::7 (Nec 5!We):

S. If Ch:=;es 0:=:in Qp:=i:y R::i:;s (1:= s Nc=ba 3 Throu;h 7) Sine: L:s: Repor:. Give Re: seas:

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9. Power L:ve! To Wh!:h R=:::.::d. !! Any (N:: Stwe):

10. Resons For R..-=i: dons.lf Aav. :

This blanth Y:.<o-Os:s Cc==I::ive 720 65G1 76,679

11. Hour: != Repor:ia; P=iod 4619.3 56,5OO.9

12. Nu.=her Cf Hou:s R::=:r W:s C:id:.1

13. Re==:r Rese. e Sh:dowr H::::

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463

14. Ec=:: Ce===:: Ca.LI:s 4610.8 55,323.7 0

321

15. U..!: R: serve Sh down Ec==

16. Cross The==:1 I:=;y Cc::=:ed (51wH}

,a oa9 117 1c, eaa c,,

a A Ao.a1 n 41 1nM.?An

17. ~ross Ee==.

! Z=.. y Gen:::::d :).1WH)

13. Ne: E==:i !I:=;y Cene=::d (5tWrI)

_4.501.984 51.o9s.48s

19. U..i: Servi =.:::::r 70.4 74m2 70.4 74.2

20. Uci: AveE: bili:7 F:ctor

21. Unit C::::i:/ :::=r(Usi=; >!rC Net) 66.2 67.2 7

65.5 64.2 21 Uni: C.20 city. ::::r(Using DER N4:3 1.1 7.9

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.3. Uni: For::d Cu::;e R::e

24. Sh : dows 5:hed !ad Over Lc 5 31or.:hs (Type. D:::.:r.d Du=:fon ofI:ch :

• S. If Sh : Dowrt A: End Of Repor: Period. Esti==:ed 3::e of S:::::p:

. 25' Units la Tes: S::::s iPnor to C====is! Ope-::fon1:

Fore =s:

Acnieved INIT'.A1. C?.!T*CA UTY l

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AVERAGE DATLY UNIT POWER LEVEL 1-DOCKET NO.

so-ais UNIT 1

DATE 1o-3-83 COMPLETED BYW.

T.

Gillett TELEPHONE 616-465-S901 MONTH sentenber 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 0

17 0

2 18 3

19 4

20 5

21 6

22 7

23 8

24 9

25 10.

25 - -

11 27 12 23 13 29 14 30 15 31 16 INSTRUCTIONS On this femat list the average daily unit pcwer level in MWe-Net for each day in the reporting month.

Ccmoute to the nearest whnla mamwat*

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50-315 DOCKET NO.

UNIT SiluTI) OWNS AND POWER REDUCTIONS D.C. Cook - Unit 1 UNIT NAME 10-12-83 DATE SEPTEMBER, 1983 COMPLETED llY B.A. Svensson REPORT AION'lli TEl EPilONE 616/465-5901 PAGE 1 of 1 S

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c su:

c Cause & Connective

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EM i iccusee c%

u 7

No.

Dale g

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,c g y givens py gg 3,,gg,,,

$6 fM Repott #

8N 0 U

Psevent Recusicuce 6

204 830716 S

720 B&C 1

N.A.

ZZ ZZZZZZ The Unit was removed from service at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on 830716 for scheduled cycle 7-8 refueling and maintenance.

The refueling and all major mainten-ance activities have been completed.

Unit start-up activities are in pro-gress. The anticipated date for re-turn to service is October 18, 1983.

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2 3

4 1:: 1orced Reason:

Mettual:

lixinbit G-Instsuctions S: Stliedulcil A linguipment I;ailine (Explain) 1 Manual for Psepasation of D.ita ll-Maintenance of Test 2-Manual Scraus.

Entsy Sheets foi 1.icensee C Refueling 3 Automatic Stram.

I:vens Repost II.l!R)l'ile INtlRIE I) Regulatoiy Res. -iclion 4-Othes (lixplain) 0161)

!!-Opesatos l' raining & license 1:xamination 1; Administsative 5

G Opes.ilional liisor flixplain)

'INlubit I S.une Somce p8/77) 11 Other (lixplaini

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns during the in accordance with the table appearms on the report form.

report period. In addition. it should be the source of explan.

If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT *. Reference the applicable in 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 />) reportable occurrence pertaining to the outage or power

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should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequennal shut down completely. For such reductions in power level, report number, occurrence code and report type) of the tive l

the duration should be listed as zero, the method of reduction part designation as descnbed in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further investigation may be required to ascertain whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num.

the positive indication of this lack of correlation should be ber assigned to each shutdown or sigmficant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power ' SYSTEM CODE. The system in which the outare or power reduction begns m one report penod and ends m another.

reduction onginated sh'ould be noted by the tw'o digit code of an entry should be made for both report penods to be sure di snutdowns or sigmticant power reductions are reported.

Exhibit G. Instructions for Preparation of Data Entry Sheets Until a umt has achieved its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not fit any existmg code should be denans-ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reducuon. Report as year. month. and day. Auaust 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit i. instructions for Preparation of Data Entr>

begms m one report penod and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

be made for both report periods to be sure all shutdowns using the followmg entiena:

or significant power reductions are reported.

TYPE. Lse "F" or "S" to indicate either " Forced" or " Sche.

duled." respectively, for each shutdown or significant power B.

If not a component fa11ure, use the related component.

reduction. Forced shutdowns include those required to be e.g. wrong valve operated through error: list valve as mitiated by no later than the weekend following discovery component.

of an off. normal condition. It is recognized that some judg.

ment is required in categorizmg shutdowns in this way. In C.

If a chain of failures occurs, the first component to mai.

general, a forced shutdown is one that would not have been function should be listed. The sequence of events.includ.

completed in the absence of the condition for which corrective ing the other components which fail should be described action was taken.

under the Cause and Correcuve Action to Prevent Recur.

rence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any exi:tmg code should be de.

beyond the end or a report penod,eount only the time to the signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensumg down time events where a component designation is not applicable.

in :he following report penods. Report duratton of outages ruunded to the ricarest renth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fastuon to amplify or tot was on !!ne should equal the gross hours in the reportmg expla n the circu.nstances of the shutdown or power reduction.

penod.

The column should include the specific cause for each shut.

down or sigmilcant power reduction and the immediate and REASON. Catepunze by letter deugnation in accordance with the table appeanng on the report form. If category H contemolated long term correcuve action taken. if appropri.

must be used.suppiy bneicomments, ate. Tlus column should also be used for a desenption of the l

majcr safety.related corrective mamtenance petformed dunna j

METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot;

'h' #U**"*I P ** h """' Y *"d * "E '* I " Y ** II' I'*** 0' REDUCING POWER. Categonee by number designation radioactmty or smgle radiation exposure spectilesily assoet.

INoie that this differs trom the Edison Electric Institute sted with the outage which accounts for more than 10 percent iEED de mitions of " Forced Pantal Ourage" and " Sche, of the allowable annual values.

r dated.dartial Outage." For these tenn>. eel uses a shange of For long textual reports contmue narrative on separate paper

'0 MW as the creak pomt. For larger power reactors.30 MW and reference the shutdown or power redu tton for tim is too smail a chanae to warrant explanation.

narrative.

W77

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k-DocketLNo.:

50-315

_E

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Unit Namn D.'C. Cook Unit l-

' Completed By:

C. E. Murphy-

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Telephone:.

(616) 465-5901-

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Date:

10/10/83 Page:

1 of 1 MONTHLY OPERATING ACTIVITIES'- SEPTEMBER 1983

-Highlights::

-The Unit entered the reporting period in Mode 5 with the. Reactor

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Coolant System at loop.

The seventh core refueling shuffle Lhas been completed and a major portion of the-Unit's repair work has.been completed.

As this reporting period comes to an' end, preparations and valve alignments are being completed for

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-Filling and Venting of the Reactor-Coolant System.

An Unusual Event was. declared at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on Sept. 22, 1983 Lwhen a tornado was sighted in the New. Buffalo area..The AB Emergency Diesel'and the Diesel Driven Fire Pump was verified operable. -TheLUnusual-Event was terminated at 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br /> when-the Berrien County = Sheriff's1 Department cancelled the. tornado warning.

Summary:

9/1/83~

The' Auto Gas Analyzer was inoperable for a 6.5 hour-period for repairs.

9/17/83 ERS-1401 and ERS-1405, Lower Containment air Particulate

.and Radiogas was inoperable for a 0.25. hour perica due to an inoperable check source for the instrument.

These

-instruments were again inoperable for a 6' hour period on 9/29/83 for C&I to make. repairs.

TheJControl Room Cable Vault Halon System remains inoperable

-as of 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 4/5/83..The Backup.CO System for the 2

. Control Room Cable Vault remains operable

-The Control Room-Fire Detection System remains inoperable as of 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br /> on 8/24/83.

Hourly fire patrols are_being conducted.

behind the Control Room Panels.

e DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-12-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1983 M-1 CVCS letdown regulating valve, QRV-lli, had a body-to-bonnet leak. Replaced the valve trim assembly and gaskets. Repacked the valve and had it tested.

M-2 Residual heat removal system containment isolation check valve, RH-142, was leaking by.

Lapped the disc and seat and reassem-bled with new gaskets. Had the valve tested.

M-3 No. 3 steam generator bloedown isolation valve, BD-101-3, had been sealed by Furmanite injection to stop a leak under pres-sure. Replaced the valvo and had NDE performed.

M-4 An electrical ground on-the 11A bus was traced to motor-operated valve, IM0-911.' Replacid the power cable to IM0-911 and com-pleted required inspections including test of the valve.

M-5 Auxiliary feedwater che :k valves, FW-138-1, 2, 3 and 4, were disassembled for a scheduled inspection. The valve seats were lapped and the discs we: e remachined. The valves were reassem-bled using new gaskets.

M-6 The impulse line to the east RHR flow instrument, IFI-330V2, broke. Removed broken saction of tubing and rewelded. Had necessary NDE performed.

M-7 During a surveillance test, _ safety injection check valve, Sl-170L3, was leaking by in excess ofithe limits established. Replaced the valve disc, gasket and two studs and nuts. Had the valve retested.

M-8 The root valve for No. 2 steam generator pressure instrument,

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MPP-242 was leaking. Replaced the valve and had NDE performed.

M-9 The tubing was broken do9nstream of the root valve for the east RHR heat exchanger flow instrument, IFI-330. Cleaned and re-welded tubing in reducing insert at outlet of the root valve.

Had necessary NDE performed.

M-10 During a surveillance test, glycol containment isolation valve,.

VCR-ll,' leaked by.

Replaced the valve diaphragm and had the valve tested.

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-^ g DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-12-83 COMPLETED BY B. A. Svensson TELEPHONE.

(616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1983 M-11 Glycol containment isolation valve, VCR-10, was sticking.

Re-placed the valve diaphragm, lubricated valve stem and had the valve tested.

'M-12 The west. centrifugal charging pump failed to deliver the re-quired flow during a. test. Replaced the pump rotating assen-bly-and the inboard seal housing. Repaired pump casing cladding.

Rebuilt the mechanical seals and realigned pump, speed increaser and motor. Had the pump retested.

M-13 Volume' control tank safety valve, SV-53, was leaking by.

Re-placed the valve disc and lapped the seat. Valve tested satis-factorily.'

M-14 During periodic inspection of service water' valves for the CD emergency diesel, ESW-114, was found to have a worn seat.

Re-placed the valve seat.

M-15 CCW motor-operated isolation valve, CM0-415, would not close ccmpletely-from the Control Room. Replaced the valve and had it tested.

M-16 Performed periodic inspection of No. 11 reactor coolant pump controlled leakage seals. Replaced No. 2 insert, seal and run-ner. Also replaced No. 3 seal.

M-17 Emergency boration isolation valve to the charging pumps, QM0-410, would not cycle. Replaced the housing for the motor operator and had the valve tested.

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IN0 LANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Mkhigan 49106 (d16) 465-5901 October 12, 1983 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, 1983 is submitted.

Sincerely, O-l rr

. C. Smith, M Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen FRC Region III E. R. Swanson R. O. Bruggce (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center 3 >d t

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