ML20082S907

Monthly Operating Rept for Oct 1983

ML20082S907
Person / Time
Site:	Cook
Issue date:	10/31/1983
From:	Might A, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8312150052
Download: ML20082S907 (8)

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OPERAT*NC DATA RE? ORT i:.

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50-315 DATI 11-9-nt C05L*! :...:.D ?.Y nmn sk+-

TI2_I?*iCNE.'C 0 465-5901 0 int!NG 5 ATUS No:38

1. Uni:N:cie:, %1a r-r~+

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% 4v'r 1 on~4

2. Reporting ? dod:'

'4790

3. U--W Tc --f ?swer piW:):

1152

- 4. N==nepist'= Re:ing (Cson ?.:W:):

1030

5. Desig:t I!=::i=1 R::ing (Nes 51We):

1056

- 6. V-m== Depend: hie Capci:7 (Cross 51We):

1020

7. Sin'---m De;-- '-'-1: C:p:=i:7 (Net 31We):

_ S.. If Ch:n; s Oc=:in Cap:=i:y R::!:;s (1::=s Nu:nh: J Threu;h 7) Size: Las:R:per:. Give R=sans:

7.h ower Levd To Whi.i R=s.6.-.:d. !! Any (N:: SIW ):

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10. R= sons For R_-.Ei:: ions.lf Any:

This Sionth Y: a o.C ::.

Cc==hdve 749 7296 77,424

~ 11.' Hoc s != R:por:in;; ?::fod 268 4887.3 56,768.9

.12. Nu=h:r Of Hou:s R==: t Was Cri:fr.t d

0 0

463

13. Ree:m: Rese:ve sh::down

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1.86.3 4797.1 55,510.0

14. Haus Gene:-:nr On.U,

0 0

321

15. Usi: R: serve Sh:tdown Ec :::

16. Cross Tht:=:1 En::;y Cen:=ted piWE) 323,110 14.565.227 161,867,787 t00,40 4,769,670-53 203,720

17. Crosr.I!c=::i=1Iser y Cen =:= i g.tWE) 01:411 4,595,917 51,189,418

13. Net 7.ie=i=1 E==;y Cen==::d C.tWE)

19. U..it Serri=.:::tae _

25_n 65.7 73.6 25.0 65.7 73.6 20.' Uni:Av.ibhiE:7 F:c:or 12.4 60.7 66.6

21. Uni: C:psci: r 7:=:r (Usi :: MDC Nec) 12.2 60.1 6 ;.7

22. Unit Cspacity F:::ce (Using DER.4et) 0 1.1 7.9

23. Uni: Fore:d Cu:: e Race

24. Sh:: downs Sched led Over Nex: 5 Mon:hs (Type.D:te.:nd 0 =:ica ofI:ch1:

Maintenance outage scheduled for 11/23/83 to repair reactor coolant hump 54.

25. If Sh:: Down At End Of R: port P=:fod. Esti==:ed D:ce of S:::::p:

.25' Units in Tes: 5::::s (P:for to C====!s! Ope =: font:

For:=st Achieved l

INITIAL CRIT *CAUTY

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INITIAL ILICTR:C;~Y CO.it.:ERC:A O?I?. 2,T ON

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8312150052 83103 PDR ADOCK 050003 5 tui-R PDR l I I

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AVERAGE DAILY' UNIT POWER LEVEL 4-00CXET NO.

sd-31 s '

UNIT 1

DATE 11-1-83 COMPLETED BY Ann Might TELEPHONE' (616) 465-5901 MONTH oc+nher, '1983

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DAY AVERAGE DAILY POWER LEVEL '

' DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1-17 2

18 3

19 4-20

-5~

21 l6 22.

7 23 8-24 176 l

. 9 25 336 10 25 445 11 27 450 i

12 28 440 13 29 622 L

14-30 658 15 31 787 16 INSTRUCTIONS 1

L On this fonnat list the average daily unit power level in MWe-Net for each day-in the reporting month. Compute t@ thcqJwuenesh

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50-315'

. DOCKET NO.

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UNIT SilUTDOWNS AND POWER REDtlCTIONS UNIT N AME D.C. Cook - Unit 1 DATE 11-14-83 COMPLETED 3:Y B.A. Svensson REPORT MON 11g OCTOBER,1983 TEl.EPHONE 616/465-5901 PAGE 1 of 1

.3 Licetisce bt Cause & Coes'eceive No.

Date g

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).gE livent h,

E3 Aciion so -

f' Prevent Hecustence

$5 sE j5g Repost 8 mO H

5 204 830716 S'

558.7 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 outage. Initial criticality for Cycle 8 occurred on 831020 and the low power physics testing was com-pleted on 831022. The Unit was re-turned to service on 831024 and was-at 90% power level at the end of the month. The total length of the out-age was 2406.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

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F: Foicet!

Heason:

Meilunt:

Exhibie G-Insisuctions S: Schetinled A Equipmer.: Failure (Explain) 1 Manual for Preparation of Daia li-Maintenance of Test

2. Manual Scrani.

Entry Sheets fin I.icensee C Refueling 3-Automatic Scram.

Event Repose O.ER) File INtlREG-D-Regulaimy Restriction 4-Ot hes ( Explain) 0161) a i

li-Ope ator Fraining& license lixamination F-Administ ative 5

t G Opciational linor (lixplain)

Exinbis 1 - Same Somce 19/77)

Il-Other (Explaint q

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..J Docket No. : 50-315=

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Unit Nam 3

-D.xC.' Cook-Unit.1

" Completed;By: ; G. - J.

Peak

~ Telephone: f(616) 465-5901

-Date:

11/8/83-

. Page :: =1;of 2

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' MONTHLY OPERATING' ACTIVITIES

~OCTOBERJ1983 Highlights:1 iThe' Unit

• enter'ed?the reporting period with-the Reactor Coolant

System 11n thejprocess of-being' filled and ventedras the-seventh s

refueling outagelcamef o an end. ' Initial' criticality of.the t ~

, eighth: core;occured and' Low Power. Physics; testing was. completed.

. Currently--the : Unit ?is in' the process of increasing to the 95%-

powe'rc. level-as?part of:theJPower'Accension Program.

Summary:

'10/1/83-

'The.High Demand: Fire Pump was inoperable from 0520. hours on 10/1 until'2233l hours on 10/6 to repair the: Suction f

Strainer.:

110/2/83

~The: West 1 Centrifugal. Charging Pump was inoperable from r

11025 hours on'10/2 until 1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br /> on 10/4 due to a-

Mechanical sealaleak.

The-Containment Hydrogen Monitoring System was inoperable from' 2100 ' hours on 10/2 until 1142. hours cn1 10/16 to repair a component cooling water piping. error that was.made during.

its installation.-

110/4/83~ 'The1 Auto GasLAnalyzer was inoperable for a 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for? repairs.-

-l10/4 / 83 The AB: Diesel Generator was -inoperable 'for a 7. hour. period

to work'on:aESafety: Valve on the Cooling WaterLSystem.

10/7/83' VRS-1101' -Upper Containment Area Monitor failed and was

~ inoperable from 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on 10/7 until 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br /> on 10/13.

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-10/10/83.The~ Fire Detection in the Rad Waste Drumming Room has been

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inoperable since:1715 hours on 10/10.

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10'/11/831 Thef CD Diesel was inoperable from 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> on 10/11 until-

.2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> on 10/12 because one of the output breakers would not close.

10/14/83 VRS-1101-

. Upper.. Containment Area Monitor was inoperable for

-a'13.5 hourfperiod'due to a standing high alarm on the monitor.

Entered-Mode 4 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

?10/15/83' Entered. Mode 3 at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br />.

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1Docktt No.:

50-315 Unit Nam 3 D. C. Cook Unit 1 Completed By:

'G.

J. Peak Telephone:

(616) ~ 465-5901 Date:

11/8/83

.Page:. 2 of 2' 10/20/83 Entered-Mode 2 at'1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> and the Reactor went critical Rat 2103' hours.

10/22/83 ILowLPower Physics testing was completed at 1032 hours0.0119 days <br />0.287 hours <br />0.00171 weeks <br />3.92676e-4 months <br />.

10/23/83 Entered Mode-1 at-1201 hours-, however problems with the turbine speed control occured and the Unit went back into

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Mode 2 at-1950 hours.

10/24/83-' Entered Mode 11 again at:0459-hours and paralleled the Unit toLthe System at 0641 hours0.00742 days <br />0.178 hours <br />0.00106 weeks <br />2.439005e-4 months <br />.

The Reactor was at 30% power at 1027 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.907735e-4 months <br /> and held there due to secondary side chemical requirements.

10/25/83 Reactor:at 48% RTP at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

10/29/83 -Raactor at'68% RTP at 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />.

10/31/83 Reactor at 90% RTP at 1713' hours.

The-Control 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 Control Room Cable 2

Vault remains ~ operable The' Control Room Fire Detection System remains inoperable as of 1435 hour0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />sion 8/4/83.- Hourly fire' patrols.are being conducted behind the.

' Control ~ Room Panels.-

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DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. l_

DATE 11-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901

.PAGE-1 of 2 MAJOR SAFETY-RELATED MAINTENANCE-OCTOBER. 1983 1

M-1

- During operation, a ' containment area radiation monitor alarmed when pressurizer spray control valves NRV-163 and 164 were cycled,-indicating a possible packing leak. Inspection revealed no-problems on NRV-164. The trim assembly for NRV-163 was re-

=placed and the valve was repacked. The valve was functionally tested.

M-2 The west centrifugal charging pump inboard mechanical seal was leaking. Rebuilt the seal and had the pump tested.

M-3 Performed periodic inspection of seals for #4 reactor coolant pump. Replaced #1 ring, runner and sleeve, #2 ring and #3 ring.

M-4~

The. east' centrifugal charging pump was disassembled to inspect the casing cladding. Rebuilt the mechanical seal and re-

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assembled pump. Had the pump tested.

-M-5 A'grounid indication was traced to a pressurizer backup heater circuit. Found a cable.with damaged insulation. ' Repaired in-sulation and. the ground cleared.

M-6 During' surveillance inspection of LAB emergency diesel, the #4 main _ bearing was found wiped. Replaced the engine base, crank-shaf t, ' main caps and all main and rod bearings. The engine was tested.

M-7 The wedge for motor-operated valve, IMO-110, safety injection isolation valve, was replaced and the valve was tested.

M Performed inspection of #2 reactor coolant pump seals. Replaced

1. 1 seal shaft sleeve and #3 seal runner.

M-9 Number 4 steam generator stop valve, MRV-240, had a broken

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linear' bearing in the crosshead. Replaced the linear bearing and tested the valve.

M-10 The ESW isolation valve to the suction of the turbine driven auxiliary feed pump, WM0-753, was leaking by.

Replaced the valve and had the new valve tested.

M-ll The refueling water storage tank outlet isolation valve, IM0-910, would not close. Investigation revealed that a nut had fallen from the mechanical' position indicator,and landed near the stem resulting in jamming of the valve. Replaced the stem nut locknut and the, operator motor. Had the valve tested.

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s DOCKET NO.

50 - 315

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UNIT.NAME

.D. C. Cook - Unit No. 1 DATE'

11-14-83

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. COMPLETED'BY

- B. A. Svenscon

!I

' TELEPHONE (616) 465-5901

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PAGE 2 of'2

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MAJOR SAFETY-RELATED MAINTENANCE

[-

0CTOBER, 1983~

'M 12

' The volume control! tank ' diverter valve, QRV-303, would not: cycle completely. Disassembled.the valve and four L-shaped bolts inside the valve. Also, found one bolt in check valve CS-396..

. Removed the bolts. Replaced'the plug, cage and o-rings in QRV-303. Reassembled ~both valves and had QRV-303 tested. The

. bolts': vere determined;.to be adapter l plate fasteners from the reactor coolant filter.

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X IMOIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT

' P.O. Box 458, Bridgman, Michigan 49106 (616) 4654901 November 14, 1983 Director, Office Of Management Information and Program Control.

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Centlemen:

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 October, 1983 it, submitted.

Sincerely, W. G. Smith, Plant Manager WGS:ab Attachments cc:

J..E. Dolan M. P.-Alexich Q

R. W. Jurgensen r

NRC Region III E. R. Swanson

/ f R. O. Bruggee'(NSAC)

R. C. Callen S. J. Mierzwa R. F..Kroeger B. H. Bennett J. D..Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center