Text

Monthly Operating Rept for Nov 1983
	ML20086G772
Person / Time
Site:	Cook
Issue date:	11/30/1983
From:	Might A, Peak G, Svensson B; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8401120398
	Download: ML20086G772 (11)
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CPERA :NC DATA RE?CRT

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DCC:CI'T NO.

50-315 DA7; 12/2/83 C05:?L.E'~r.D EY A-Might TEL.Z?.'iCNE. ' A1 A1 ^ ^ 5-5 9 CPI?x !NC 5""ATUS N0f:8 Donald C. Cook 1

g, gagg y,,,.

NOVEMBER 1983

., Repor:is;.3.a.cc 3250

3. U--WTht:=:1?:wer(SiW:!:

1152

4. Ns=eplate Rui.;(Gross 51We): _

1030

5. Design E!c=i=1 Ar.:ing(Nec51We):

1056

6. y-"-:=== Depe.dshte Cap:ci:y (Gross 51We): 1020 T. Si=s- -m Depe=d:ble C:p:d: / (Ne: 51We):

S,. If Ch:=;;s Oc=::in C:pz=i:7 R::i ;s (1::=s Nu:nb:: 3 Throu;h 7) Sinc: Lis: Repor:. Give Re: sons:

s

9. Power Leve! To Which Rer=i:: d.If Any (N : MWe):

10. Re: sons For R_-.::i:: ions.!f Asy:

This Month Y.<o-Catt.

Cu=chtive 720 8016 79.144

11. Hou:s In R ponis; P::fod 524 5411.3 57.292.9

12. Nu h:r of Hou:s R==:ct W:s C:i:ict

0 0

463

13. Rec:cr R=sene Sh ::!own E :.:s

.524 5321.1 56,034.0

14. Hours Gene ::e Cn-Lins 0

0 321

15. Uni: R: serve Shutdow= Ec===

1,476,269 16,041,496 1s1 7aa nnc

16. Cross The:=:1 En ::y C4..:=: d (MWI-!)

483,410 5,253,280 c; 3. 6 R o.11 n

17. Cross Se=i=1Iser y Gene =: d G.IWH) 464,611 5,060,528 51.654.029.

13. Net E==i=lIntr;y Gene =: d C.tWi-D 72.8 66.4-73.6

19. Unit Serri=.::: tor

-72.8 66.4

.n F

10. U:!: Av:ibbi!I:7 :::or

.J 60.9~

66.

21. Unit C:: sci:/ F=:: r (Usi=; MDC Net) 6216 60.1 63.7 I

2":. Unit Caescity F:::or(Using DER.4et

9 44 1 a i

23. Uni: For :d Cu::ge Rste l

24. Shutdons Scheduled Over Nec 6 Mon:hs (Type. 0:te.:nd Oc=: ion of Z:cht:

l l

12/13/83

15. If Shu: Down At End Of Report ?::iod. Esti==:ed D:te ciStar=p:

25'. L* nits In Tes: 5::::s IPrior to C====is! Ope =: font:

Fore =st Achieved i

INIT:AL CRIT:CALITY

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IN;TIAL I* ICTR:CI-'Y CO? *:.;I?.C:A L 0?E7.A7:0N I

FIII B401120398 831130 PDR ADOCK 05000315 i.

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AVERAGE DATLY UNIT POWER LEVEL

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00CXET NO. 50-315 UNIT 1

DATE l'2/2/83 COMPLETED Bf A. Might TELEPHONE (616) 465-5901 MONTH unvrunnn 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 o,o 17 596 2

973 18 981 3

975 19 911 4

979 20 838 5

982 21 798 6

979 22 582 7

1023 23 8

1032 24 9

1034

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25 10 1033 25 11 1936 27 12 1036 28 13 969

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29 14 554

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30 15 553

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31 16 552 INSTRUCTIONS On this format list the average daily unit pcwer level in MWe-Net for each day in the reporting month.

Ccmoute to the nearest whnia mecawatt.

i DOCKET NO. 50-315 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 1 DATE 12-15-83 NOVEMBER, 1983 COMPLETED itY B.A. Svensson NEPORT Af0 Nill TELEPilONE 616/465-5901 PAGE 1 of 2 "i

.$ E 3

Yk Licensee 5 r, hg Cause & Connective No.

Dale 9,

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Even 3y

o. 3 Action to g$ 5 jgg Reposter id u O

Prevent Recurrence 6-6 205 831113 F

0 A

4 N.A.

CH ZZZZZZ Reactor power was reduced to 55% to remove the east main feed pump from service to repair tube leaks in the feed pump turbine condenser. One tube was plugged. During power re-covery on 831114 with the reactor at 70% power, the coupling iailed on the east main feed pump. The pump was manually tripped and reactor power rapidly reduced to 56%. The entire coupling assembly was replaced on the pump and returned to service on 831117. Reactor power was returned to 100% on 831118.

206 831119 F

0 ASB 4

N.A.

HF PUMPXX Reactor power was reduced to 83% to remove the No. 13 circulating water pump from service for repair of the pump bearings. On 831121, reactor power was further reduced from 83% to i

2 3

4 1:: 1mced Reason:

Methial:

Exhibit G -Instructions A-Eiguipment li ilure (Explain) 1 Manual for Picpasation cf Data S: Scheiluleil a

ll-Mdulenance of Test 2-Manual Sceam.

lintiy Sheets fm l_icensee C-Hefueling 3 Automatic Scram.

Event Repose (I.l!R)I ile (NllHl:G-D Hegulasmy Restsiction 4 Other (lixplain) 0161)

ILOpesalm l'asining & l.iccuse lixamination IL Aihuinist sative 5

lixtubit 1 - Same Somce G Opesational Enor (lixpl.un) pl/77) 11 Othes (Explain)

1 UNIT SHUTDOWNS AND POWER REDUCTIONS

' INSTRUCTIONS This report should deserte all plant shutdowns dunng te in accordance with the table appearmg on the report form.

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

If category 4 must be used. supply brief comments.

anon of sigmncant dips in average powe: 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 preecding 24 hoars) reportable accurrent pertatnmg to the outage er power mould be noted, even thouzh the unit may not have been reductio. Enter the first four parts (event year. sequent:al shut down completely. For'such reductions in power level, report number, occurrence code and report type) si the five l

the duration should be listed as zero,the method of reducuan part designation as desenbed in Item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data Entry Sheets for Licensen Event R. port Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). Th:s information may not ce Cause and Correenve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

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

NUhlBER. This column should indicate the sequential num-the postuve indication of this lack of correlation should be ber assigned to each shutdown or signincant reduction ta power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power reduction begins in one report period and ends in another.

SYSTE31 CODE. The system in which the ou.tage or power an entry should be made for both report penods to be sure reduction anginated should.ce noted by the two det code or.

all shutdowns or significant power reducuons are reported.

Exhioit G. Instructions for Preparation of Data Entry Sheets Until a unit has achieved its ficst power generation, no num-f r Licensee Event Report (L !R) Fi!e (NUREG.0161).

ber should be assigned to each entry.

Systems that do not nt any existmg code should ce designa.

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 signincant power reduction. Report as year. month. and day. August 14.1977 would be reported COSIPONENT CODE. Select the most appropnate component as 770814 When a shutdown or sigmficant power reduction from Exhibit !. Instructions for Preparanon of Data Enm begmsin one report penod and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.01615.

be made for both report periods to be sure all shutdowns usmg the following critiena:

or significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled." respectively, for each shutdown or significant power B.

If not a component failure, use the related compone.t:

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

of an off normal conditim. It is recegnaed that some judg.

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

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

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 wluch 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 beyond the end or a report penod, count only the time to the Components that do not nt any existmg code should be de.

signated XXXXXX. The code 777777 saould be used fcr end of the report penod and pick up the ensuing down time events where a component designation is not appli:able.

in the following report penods. Report duranon of outages rounded to the nearest tenth of an hout to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

RENCE. Use the column in a narrative fastuon to amei.f> cc tot was on line should equal the gross hcurs in the reportmg explap. the circumstances of the shutdown orpower red'uenon.

penod.

The column should melude the specific cause for each shut.

down or significant power reduction and the immediate and REASON. Categonze by letter designation in accordance with the table appearmg un the report form. If category H contemplated long term correenve action taken, if appropn-must he used. supply bnet comments.

ate. This column should also be used for a desenpt;en of the major safety.related corrective maintenance performcd dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an :dentincation of REDUCING POWER. Categonze by number designation the enucal path acuvity and a report of any smgie release at radioactivity or single radiation exposure specincollv nsect.

INote that this differs trom the Edison Electne Insutute ated with the outage which accounts for more than O tereent TEED denrutions of " Forced Parnal Outage" and "Sc:.e.

of the allowable annual values.

duled Partial Ourage

For these tenna. eel uses a shange or' For long textual reports continue irranve on separ,. ; : aper 30 31W as the break romt. For larger power rentors. 30 StW

.nJ referen;e the shutdown or ower reduonon no an,

s im small a change to wanyu nplanation.

narrative.

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DOCKET NO.

50-315 UNITSilUTIM)WNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 1 DATE 12-15-83 HEPORT MONTil NOVEMBER, 1983 COMPLETED BY B.A. Svensson TEl.EPilONE 616/465-5901 PAGE 2 of 2

.E E 3

Y l icensee 53, h.,

Cause & Censective No.

Date g

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.E s s I!vens p; g o.1 A ui4m in

$6 5

35F Repeua #

di'O hU Prevent Hecinrence H

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eQ 206 (( ont'd.)

70% to inspect and clean condenser waterbox tube sheets due to an ex-cessive amount of trash in the cir-culating water system.

207 831122 F&S 196.0 A&B 3

N.A.

ZZ ZZZZZZ At 1958 hours0.0227 days 0.544 hours 0.00324 weeks 7.45019e-4 months , the west main feed pump turbine tripped due to low vacuum with a resulting reactor /tur-bine trip one minute later due to low feedwater flow. The Unit had been scheduled to be shut down the following day for reactor coolant pump motor and valve maintenance.

The Unit was therefore kept out of service and remained out of service at the end of the month.

I 2

3 4

F: Foeced Reason:

Me:Imd:

Exinbii G - Instincai4ms S: St heilnleil A-liipupment Failuie(Explain) 1 -Manual for Pseparaison of Data li-Maintenance of Test 2 Manual Seeam.

liniiy Sheets fm 1.icensee C Refueli.ig 3-Automatic Scram.

Event Report II.l!Rll'ilelNilRl!G-

1) Regulatosy Resinicsion 4-Ot hes ( Explain) 0161)

I!-Opesaios I'saining & License lixamination F-Administ sative 5

G Opesalianal Essur (Explain) 1!sinbit I Same Sinnce P8/77) ll Other (Explaini

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

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

If catepry 4 must be used. supply brief comments.

atton of sigmilcant dips m aserage power levels. Each signi.

~ ficant reduction in power level (greater than 20'5 reduction LICENSEE EVENT REPORT. Reference the app!icable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reponable occurrence penammg to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four pans (event year, sequent:al l

shut down completely. For such reductions in power level, report number occurrence code and report type) of the tive the duration should be listed as zero, the enethod of reduction part designation as described in item 17 of Instruenons for should be listed as 4 (Other), and the Cause sad Correenve Preparation of Lats 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 Correedve Action to Prevent Recurrence column immediately evident for all such shutdowns, of courm smee should be used to provide any needed explanation to fully further investigatica may be required to ascertam whether ur 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 orsignificant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmftcant power -

SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends m another.

an entry should be made for both report periods to be sure reduction onginated should be noted by the two digit ecde of

11 shutdowns or sigmilcant power reduedons are reported.

Exhibit G Instructions for Preparation of Data Entry Sheets Until a unit 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 designs.

ted XX. The code ZZ should be used for those events where DATE. This column should indicare the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year. month. and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770314 Whm a shutdown or significant power reducnon frcm Exhibit 1 Instruenons for Preparation of Data Entry begmsin one report pened and ends m 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. Use "F" or "S" to indicate either " Forced" or " Sche.

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

If not a component failure. use the related component:

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

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

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

If a chain of failures occurs, the fir't 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 desenbed action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Self. explanatory. When 5 shutdown extends Components that do not fit any ex2stmg code should be de.

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

in the followmg report penods. Report duration of outanes rounded to the nearest tenth 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 tor was on line should equal the gross hours in the reportmg explain the circumstances of the shutdown orpower reduenen.

pedod.

The column should include the specific cause for each shut.

down or sigmilcant power reduchon and the immediate and REASON.- Categonze ay letter designation in accordance with the table appeanng on the report form. If category H contemolated lona term correenve action taken. if appropn.

ste. This column'should also be used for a hsenption of'he must be used, suppiy brief comments.

maior safety.related corrective mamtenance performed dunng 5

METHOD OF SHUTTING DOWN THE REACTOR OR e outage r p wer reduction including an identtilcation of REDUCING POWER. Categonze by number designation the entteal path aetmty and a report of any smgle release of, radioactmty or single radiation exposure speettically assoes.

1 Note that this differs trom the Edison Electric Institute sted with the outage which accounts for more than :0 percent (EEI) definitions of " Forced Partial Outage" and -Sche.

of the al%aole annual values.

duled Partial Outage " For these terms. hEl uses a shange or For long textual reports contmue narrative on separate paper

0 MW as the break nomt. For larger power reserors. 30 MW and referense the shutdown or power redu tion for itm is im small a change to warrant esplanation.

narrative.

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Docket No.:

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

G.

J.

Peak Telephone:

(616) 465-5901 Date:

12/7/83 Page:

1 of 3 MONTHLY OPERATING ACTIVITIES - NOVEMBER 1983 Highlights:

The Unit entered the reporting period holding at the 95% power level as part of the Power Accension Program following the seventh refueling outage.

Major power reductions occurred to remove the East Main Feedpump from service to search for condenser tube leaks and to remove the #13 Circulating Water Pump to repair a bearing.

The Unit tripped one day prior to the day a scheduled outage was to begin to repair the #14 Reactor Coolant Pump and a Pressurizer Spray Valve.

The cause of the trip was steam flow / feed flow mismatch on #12 and #13 Steam Generators due to the West Main Feedpump tripping on low vacuum.

A pressure transient was experienced after the trip and during recovery Pressurizer Safety Valve SV-45B opened prematurely at 2235 psig.

Pressure dropped to 2100 psig and the safety went shut.

All three Pressurizer Safety Valves will be removed and tested during the outage to ensure they operate properly.

As the reporting period came to an end, the Unit was entering the second week of an estimated three week outage.

Total electrical generator for the month was 493,410 MWH.

Summary:

11/2/83 The fuel handling area exhaust fans have been inoperable since 1321 hours0.0153 days 0.367 hours 0.00218 weeks 5.026405e-4 months to make repairs to the Rollomatic Filter.

11/3/83 VRS-1101 (Upper Containment Area Monitor) was inoperable for a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months period for trouble shooting.

11/7/83 Power reached 100% for the first time following the seventh refueling outage at 0633 hours0.00733 days 0.176 hours 0.00105 weeks 2.408565e-4 months .

The diesel driven fire pump was inoperable from 0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months on 11/7 to 1614 hours0.0187 days 0.448 hours 0.00267 weeks 6.14127e-4 months on 11/19 for a maintenance surveillance.

11/8/83 The #2 Boric Acid Transfer Pump was inoperable from 1238 hours0.0143 days 0.344 hours 0.00205 weeks 4.71059e-4 months on 11/8 to 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on 11/9 for maintenance work.

11/10/83 Began removing the Unit from service at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months due to both trains of Containment Hydrogen Monitoring System being declared inoperable because of low heat trace temperatures.

Train B was declared operable at 0148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months and the power reduction then stopped at 95%.

The Unit was returned to 100% power at 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months .

VRS-1101 (Upper Containment Area Monitor) failed and was inoperable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period.

f Docket No.:

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

G. J.

Peak Telephone:

(616) 465-5901 Date:

12/7/83 Page:

2 of 3 11/13/83 Power was reduced to 55% at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months to remove the East

\\,

Main Feedpump from service to search for condenser tube leaks.

11/14/83 One leaking tube was plugged in the East Main Feedpump Turbine Condenser.

A fire occured on the East Main Feedpump at 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months due to a failed coupling between the turbine and the pump.

Power was reduced from 70% to 56% at 0612 hours0.00708 days 0.17 hours 0.00101 weeks 2.32866e-4 months .

ERS-1300 (0pper Containment Airborne Monitor) was inoperable for a 40 minute period due to a flow circuit problem.

11/17/83 Repairs were completed to the East Main Feedpump coupling and a power increase began at 1410 hours0.0163 days 0.392 hours 0.00233 weeks 5.36505e-4 months .

The power increase stopped at 97% to investigate prob].ms with the #13 circulating water pump.

11/18/83 Power increased to 100% at 1920 hours0.0222 days 0.533 hours 0.00317 weeks 7.3056e-4 months .

A fire occured in the AB Diesel Generator Room at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months .

The cause of the fire was the Exhaust Fan Control Transformer.

The fire was out at 1102 hours0.0128 days 0.306 hours 0.00182 weeks 4.19311e-4 months .

The fire damaged the supply cable to the Train B "N" Train Battery Charger, which was inoperable for nine hours for repairs.

11/19/83 Reduced power to 83% at 0942 hours0.0109 days 0.262 hours 0.00156 weeks 3.58431e-4 months to remove #13 cire. Water Pump from service.

11/21/83 Reduced power to 76% at 2157 hours0.025 days 0.599 hours 0.00357 weeks 8.207385e-4 months to maintain Condenser Delta T below 27"F while condenser halves were being removed for trash inspection.

11/22/83 Reduced power to 72% at 0708 hours0.00819 days 0.197 hours 0.00117 weeks 2.69394e-4 months to keep Condenser Delta T below 27*F.

West Main Feedpump tripped at 1958 hours0.0227 days 0.544 hours 0.00324 weeks 7.45019e-4 months due to low vacuum.

Reactor and turbine tripped at 1959 hours0.0227 days 0.544 hours 0.00324 weeks 7.453995e-4 months due to steam flow /

feed flow mismatch on #12 and #13 Steam Generators.

Safety Valve SV-45B opened prematurely at 2235 psig.

The Safety went shut at 2100 psig.

11/23/83 Entered Mode 4 at 0401 hours0.00464 days 0.111 hours 6.630291e-4 weeks 1.525805e-4 months .

11/24/83 Entered Mode 5 at 0911 hours0.0105 days 0.253 hours 0.00151 weeks 3.466355e-4 months .

11/27/83 Reactor Coolant System drained to half loop at 1458 hours0.0169 days 0.405 hours 0.00241 weeks 5.54769e-4 months .

c.

' Docket.No.:

50-315 Unit Names D. C. Cook Unit 1

' Completed By:

G.

J. Peak Telephone:

(616) 465-5901 Date:

12/7/83 Page:

3 of 3 The Control-Room Cable Vault.Halon System remains inoperable as of 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on 4/5/83.

The back up.CO System for the Control Room 2

Cable Vault remains operable.

The. Con' trol Room Fire Detection'dystem' remains inoperable as of 1435

~ hours on 8/4/83.

Hourly fire patrols are being conducted behind the Control Room Panels.

l l

(??ll A.-

3 DOCKET NO.-

50 - 315 UNIT NAME D. C. Cook - Unit No. 1~

DATE 12-15-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE:

1 of 1 MAJOR SAFETY-RELATED MAINTENANCE' NOVEMBER. 1983-M.1 -

The north waste gas compressor.would not develop a suction on the waste gas header. All of the diaphragm valves in the suction piping were inspected and found to be in good condition.-

The stem nut of one of the suction check valves, WD-220N, was missing. Replaced the nut and searched for the missing nut, with no success.

M No._22 steam generator stop valve drain valve, MS-135-2, had a body-to-bonnet leak. Replaced the valve and had necessary NDE performed. Completed a leak test at operating pressure.

M Radiation Monitor VRS did not have proper sample flow.

Re-placed the sample pump.

M-4 The east RHR pump recirculation valve, IM0-312, would not close from the control room. Reset the motor operator bypass limit switches and had the valve tested.

C&I-l Spent fuel pit air rollomatic filter auto-advance mechanism was erratic in operation, causing the filter paper to bunch up.

The advance timer circuit was checked out and the mechanism was adjusted to correct the problem.

C&I-2 Steam Generator No. 1, feedwater flow rate instrument channels disagreed when at 56% reactor power. Flow transmitter FFC-210 was removed from service and was recalibrated.

'C&I-3 Delta T/Tavg-Protection Set I overpower reactor trip and rod block bistable TB-411G/H failed, and was replaced with a spare unit.

C&I-4'

-Unit vent effluent monitor VRS-1500 " low sample flow" alarm was received. The tritium collector was leaking due to scored sample plug "0" rings. The "0" rings were replaced. Loose tubing connections were tightened. Post-accident sample line

'asco valve, VS0-1530, was relieved of a piece of grit which was allowing blow-by through the valve. Flush air supply reg-ulator pressure was set at 15 PSI, causing the tritium detector plug to be blown out of its housing when the unit was in the

" flush" mode.. The regulator was readjusted to supply the correct 5 PSI.

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Y G'";",. INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 December 15, 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 November, 1983 is submitted.

Sincerely, (A

k W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson

'R. O. Bruggee (NSAC)

R. C. Callen S. J. Hierzwa 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

,h i'

ML20086G772

Text

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