Text

Monthly Operating Rept for May 1983
	ML20077A014
Person / Time
Site:	Cook
Issue date:	06/13/1983
From:	Might A, Will Smith, Svensson B; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8307220097
	Download: ML20077A014 (10)
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.s 50-315' DCC'C'NO.

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i. LI?HCNg (616) 465-5901 cpi n T!NGs ATUs L

DONALD C. COOK 1

Nor:s

1. Uni Nause:

MAY 1983

2. Reportis;?:::. d:

3250 o

3. LicansedTh --f ?ower(htW:):

1089

4. Nameplais R:rin;(Cross 5 We): -

1054

5. Design Ile==i=1 R::in: (Net 51We):

1080 g, y.Amum Dependshls Capsci:y (Cross 51We):

1044

7. af axi=== Dep- ' ' le C:p:: fry (Net 51We).

8. If Ch:rr;es Oc: urin Capaci:y R::i=;s (It==s Nu:nhar 3 Through 7) Sice: Las: Repor:. Give Rassens:

8

9. Power Level To Which R ::: iced !! Any (N:: 51We):

10. R= sons For R.-.::i:: ions.lf Any:

This 5tonth Y <o.Cata

.u=u!:tive 744

~

3,623 73.751

11. Hours != Repor:!a; P::fod 695.5 3.537.3 55.418.9

12. Nu=her Cf Hou:s R==:ce was cri:!=1 0

0 463

13. Re:::or Rese:ve Shu::iown Ecu:s 691.9 3.530.6 54.243.5 l

14. Hours Ce==:sr ca.L! e 0

0 321

15. Uni: R.-serve 5*n=tdown Ec.=

2.075,555 11,115.716 158.418.276

16. Cross The= 1 En=r;y Ce==: d (5 WM) 679,470 3,654,510 52.090.360

17. Cross Ele =:::=!Incr;;y Cent =: d (5tWM) 654,090 3.526.011 50.119.512

13. Ne: Ele==i=1 In :;y Genen: d (.'.iWE) 93.0 97.4 75.8

19. Unit Se:ric= F:ctor 93.0 97.4 75.8 F

20. Uni: Av ilabill:7 :c:or 84.2 Q3_?

An_7

21. Unit C:: sci:7 F::: r(Usin; SIDC Net) 83.4 92.3 65.7

22. Unit Capacity F:::or(Using DIR.9et) 7.0 1.5 8.1

13. Unit Forced Cu::ge Rat-

4. Shutdowrts Scheduled Over Nec 6 Ston:hs (Type. 0:te.:ri Du=:fon af I: chi:

Refueling outage scheduled for 7-8-83

35. If Shu: Oown A End Of Reper: ?::iod. Z:ti==:ed D:te oi Sts:: p:

.25'. Units In Tes: 5::::s Prior o Ce==ercial Ope =: font:

Fore =st Acaiered INITIA1. CRIT *CALITY

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INITIAL I'.ICTR:C;W ContaiET.C:A:. CPIRA7:CN tuj ;i l*

8307220097 830613 PDR ADOCK 05000315 R

FDR

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AVERAGE DALLY UNIT POWER LEVEL

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DOCKET NO.

50-315 UNIT 1

DATE 6-2-83 COMPLETED BY A. Might TELEPHONE (616)465-5901 MONTH May, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1034 17 1035 2

1035 la 1035 3

1034 19 1028 4

10J4 20 1034 5

1033 21 1021 6

1030 655 22 7

1029 23 1031 8

1034 24 1030

~

9 1033

~

25 642 10 1033 25 432 11 1035 27 501 12 1033 gg 7

13 1033 29 14 1028 30 403 15 1033 876 31 1033 INSTRUCTIONS On this fonnat list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

IMM KEl NO. 50-315 UNITSilullHlWNS ANI) POWER HEllUrlIONS D.C. Cook - Unit 1 UNil' N AhlE IIA'I E 6-13-83 COktel EIEn siv B. A. S rensson HI POR I' klONill MAY, 1983 1 El.lfilONE 616/4'35-5901 SHEET 1 o f 2_

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l*ievcses Ree issscesie 6

199 830521 F

0 B

4 N.A.

CH ZZZZZZ Reactor power was reduced to 55% to remove the west main feed pump tur-bine from service to repair a steam leak on a steam supply piping drain connection. Reactor power was re-turned to 100% on 830522.

200 830525 F

1.1 B

1 83-047/015-0 CD VALVES An internal audit discovered that Technical Specification 4.7.1.5.b required surveillance testing on the steam generator stop valves had not been performed during the March 25, 1983 outage. The unit was removed from service and the 4 valves were tested successfully. The unit was immediately returned to service.

The unit was loaded to 55% and held at this power level based on System load demand.

I 2

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.I In l'osreil Reason; hicihuit; lininini G lusisminims S: Sa hcif ulcal A l'apiipmes. 1 ailme (1:nplain)

I hianual los recpasainm ul ll.H.i 11 hlaisalenance or Test 2.klan ual Ses am.

I saiy Sheets sin Ii.cosce r Hefueling

.l. Autom.stic Liam.

then Repini 111:lt) It le INilRI G-a D ltegulatosy itestsiclion 1 Othes llimplanil 01 g,11 1 Opesaios haming& Ilocuse 1 xaminaison

12. Ailmuusisasive 5

talnini I. Same Somce G Opesau. ;al luns Ilhplaml P8/1/1 11 Hibc (lisplaint 8

UNIT SHUTD0hNS AND POWER REDUCTIONS LNSTRUCTIONS Th:s report should desente 2:1 p!2nt shutdowns dunng de m =:ordan:e with de ts:le apt.earms en de sport form.

report penod. In addit.on. tt snould be the sour: of explan.

If estegory a must be used. suppiy bnef :mments.

anon of sigmnant Jips :n svenge powe:inveis. Each upi.

n:2nt redu:non m power level (Fester man M redu non L!CENSEE EVENT REPORT =. Reference ce app':sb!e a

m 2versse dauy power level f:t me pre: ding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportsole oc:urrence pertsemg to de outsge or power

!8dW OC3- : M' 28 SIM :C'Jt 72M1 Wat F8M 38428 0'"

should be.oted. even dog;h de urut may not have been snut dowrt completely For su:h reducuens in power !< vel.

report number, o=unence : de and spon type; of tne nye l

tne dursuon should be !!sted as :ero.the method of reducten pan des:panon as desenbed b Item 17 of Instruencns for should be '.!sted as 4 (Other), 2nd de Cause sad Cctre:nve Pn=arzue of Dats Entry Sheets for Licensee Event Re:crt A:tien to Prevent Re:urrence =lumn should exp12m. The tLER) File (NUREG4161). Th:s informauon =sy not :e C.use 2nd Corre:nve Acnen to Prevent Re:unence column immediately evtdent for til such shutdowns. of curte, sm:e should be used to provide ny needed explanation to fully tuttner :nvest:gauen wty be.ecutred to ascertam whetner or desence the circumstances of the outage er power redu.:tien.

not 2 aport 2ble oc:unence was involved.) If the outsge or power reduct:en wul not result in 2 reports:le oc:ur:ence.

NUMBER. T'us =lumn should indi::te the sequential num.

the posittve mdiestion of this lack of.me!stion shocid ce ber asuped to each shutdown or sigmne:nt reducuca m power noted as not applicabie IN, A).

for that e21endar year. When a shutdown or s:gmncant power SYSTEM CODE. The, system in whi:h the outage or power reducuan begms e one report period sad ends :n another.

an ente should be mace for both report penods to be sure reduenon or:gmated should be noted oy the two d:g:t code or.

exmmt G. Insuu ncas :.or Paparsuon of Data Enuy :..nms ul snutdowns or sta:un:2nt power reduenens are reported.

Until a unit has 2:h'ieved its 6:st power generation. no num.

for Licensee Event Re: ort (LER) r, de (NL, REG ~,!61).

ber should be assiped to each entry.

Systems that de not fit any existmg code shoula :e destp2' ted XX. The :oce ZZ should be used for dose events where DATE. This column should mdicate the date of the start a system is not appliesele.

of each shutdown or signtncant power reduenon. Report as year. =cnth. And day. Aupst 14.1977 would be reported COMPONENT CODE. Sels:t de most s;prepnate omponent as 7 CS14. When a shutdown or sigmn:snt power reducten from Exhstt I Instruenens ior Preparanon of Data Ent:)

bag:ns m ene report pened and encs m another, an entry should Sheets for Licensee Event Report (LER) Fi'e(NCREG41611.

be made for botn report peneds to be sure all shutdowns usmg the followmg :ntiena:

or s pin:snt power redu:tions are reported.

TYPE. Use "F" or "S" to indicate e:ther "For:ed" or " Sche.

Juled." respecavely, for each shutdown or sipincant power B.

If not a component fa2!ure. use de re!sted ecm:enent:

ndu:aon. Forced shutdowns indade those required to be e g.. wrong valve operated throup enon list valve as mattsted by no later than the weekend fo!!awmg dis:cvery comconent.

l of an off. normal condition. It is recepi:ed that some judg.

~

ment ts required in estegonz:ng shutdowns in this way. Ir.

If a chain of failures occurs. the nrst ctnponent to nai.

gener21. a forced shutdown is one dat would not have been funenen should be listed. The secuctee of events. meind.

l completed in the usen:e of the ::ndition for which correctivt ing cc other components which fail. should be des:nbec acucn was taken, under the Cause and Corre :ve Acton to Prevent Recut-l rence column.

I DURATION. Self. explanatory. When a shutdown extends Comeonents that do not nt :ny ex:stmg : ode should be de.

beyond the end or 2 report penod. count only de time to de signa'ted XXXXXX. The : de 222222 shouid be used for end or the report pened and pick up the ensumg down time events where 2 cornponent desipation is not speiic:cle.

. m the foi!owmg report peneds. Report duration of cutages l

rounded to tne ne2 rest tenth of an nour to facditste summatten.

CAUSE i CORRECTIVE ACTION TO PREVENT RECUR.

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

RENCE. Use the sciumn in a narranve issh:on to ampitfy or l

tor was on line snould equal the gress hours in the report =g explain de cir:umstances of the shutdown orpower recuenen.

I pertod.

The ;clumn shcuid m:!ude the spectn: :suse for each snut.

down or namne:nt power reduenon and the immediate 2ec l

REASON. Categunze M.etter deugnanon in accordan:e centemelatid !ong term corre:nve senen taken. if appropn.

with the tabie appearmt on tne report form. If :stegory H ste. T'us column should also se used for a descnetion of tne t

must be used, suppiy bnet comments.

maior safety.re!xed correenve mamtenance perfomted dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outsge or power reducten in:!uding an :denpnc: tion ot; D' #U"'*I E3*h ## " *F *"d * "E " 3' *"Y 8*I" * **# #I I

REDUCING POWER. Categonze ey numner deszpsuon radioacmty or smgie radisuon ex:csure speeldesdy assee:.

Wie that this differs trom the Edison E:estn: Insuture 2ted with the out:ge which ae:cunes for more tnan 10 :ereent l

(EEli denrutions of " Forced Parnal Outage" and " Sche.

Gid* 21Io*2cie snnual v21ues.

l Juled Partial Outag." For these temin. eel uses 4 shange at For long textusi re: orts eentinue narr:nve on se:2rste ps:er l

JO MW as the break rumt. For larger power resetors. 30 MW

.nd aferen.e the shutdown or power recu. nun u 1:m

s e.u > mall a.hante tu *anunt aplanaimn.

narrative.

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IMMJKlil NO. 50-315 IlNIISilllTisOWNS AND POWEH HEllVCIIONS D.C. Cook - Unit 1 UNII N AhlE IIATE 6-13-83 COhfPililliD Hy Bd. Svensson Ill2PORIklONill MAY 1983 l El.i.FilONE 616/465-5901 SHEET 2 of 2 e.

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201 830528 F

51.0 A

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N.A.

HA INSTRU While testing the " Power-Load Un-balance" trip circuit with the re-actor power at S5%, a turbine load runback occurred due to a failure of the H.P. turbine exhaust pressure transmitter which represents turbine load in the Power Load unbalance circuit. The load runback caused a i

shrink in the steam generator levels which resulted in a reactor trip from Lo-Lo steam generator levels. A con-tainment inspection revealed a leak at pressurizer spray valve, NRV-163, 5 tem leakoff connection. To accom-plish repairs the RCS had to be cooled down and depressurized to 4000F and 400 psig. The unit was re-turned to service on 830530 and re-actor power increased to 100% on 153053J..

I 2

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12: 1:en ceil Heas.ni; kletten 1:

1:alnin G Insinan.ms S: Llicilnical A lignepnier. l - 8 uc (1.mplaii.)

I klannal len Psepau n..n al D ;a il klainicnance

'est 2-klannal &s. ins.

lini y Slicess len I.i cusce C Hefueling l Antoni.rtic St.nu.

14ent Mcpun ll l'It I ble INilHI G.

In itegulahny itessiicsion

-l Oihes (lixpland ninii l' Opcuans lunung & I ncuse I maaninanon 1: Ailinsnestuuve 5

G Operation.sl 1:nus ilhplanil 1%Intne 1 Saane Senuce 19///l 11 Ollies (Ibplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report saould desence 2!! plant shutd:wns tunns the

= ::::rdance anh me :2:le ao:carmg en the report form.

report penod. In addit:en. tt snould be the sour:e of explan.

If;2tegory 4 must be used. 2uppiy br:ef:omments.

anon of sigruncant dips a average power levels. Essa signi.

LICENSEE EVENT REPORT :. Reference de appli:2bie

$: ant reduenon m power level (gre2ter $sa 20": redu:non m 2ver2;e daily power leve! for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportsole ac:unence pertammg to de outage or po-er ecu:nen. En'er me %

cur pans (ewnt fear. sequents.

srtould be noted, even 1ough de urut =2y not have been shut down ecmpletely. For such reductens in power :evel.

report number. oc:unen:e code and report type > or tne nye l

tne duratton should :e :isted as :ero, the rnedod of reducucn part dengnation as des:nbed in item 17 of Instruenons far srtou!d be isted as 4 (Oder). 2nd de Cause and Corre:nve Preostanon of Data Entry Sheets for L::ensee Event Repert Aenen to Prevent Re urrence column should explam. The LLER) File (NUREC4161). Tbs mformauan may not ce Cause 2nd Corre:nve Acuan to Prevent Recunence column irnmediately evident for all such shutdowns, of course since should be used to provide any needed explanation to fully iuttner mvesugation may be reqmred to ascertam whetner er desence the circumstances of tne outage or power reductica not a reportable oc:urrene: was involved.) !! the out2;e or power redu:non wtil not result in a reports:le oc:urren;e.

NU31BER. Tbs :ciumn should ind!:ste the sequential n's n.

the positive mdicancn of 2:s 12ck of ctre! anon should be bet assigned to each shutdown or sigmncant reduction m power noted as not appil:2ble IN, A).

for that calendar yest. When a shutdown or sigmdcant power SYSTE31 CODE. The system m wh::n the outage or pcwer reduction begms m one report pened and ends m 2nother.

p^uden origmated should be noted oy the two d: git code o 2a entrv should be made for both report penods to be sure

'* 2D" C ' In5"U4"C"8 I ' II'E3 2 for Licensee Event Report iLER) ru."C" Cf Dats :ntry a 31 snutdowns or sigruncant power redu nons are reported.

e (NL. REG 4161).

Unt:12 urut has 2:hieved its first power generation. no num.

ber snould be assigned to e2en entry.

Systems dat do not fit any existmg ode shouic :e dengna.

ted XX. The :oce ZZ should be used for dose events where DATE. This column should indicate de date of de start 2 system is not 2:pii:2 ele, of each shutdown or signin: ant power reduenon. Report as year. menth. 2nd day. August 14.19"7 would be reported CO31PONENT CODE. Se:::t de most apptcpriate ;omovner t as 770514 When a shutdown or stinificant power reducuon from Exhtett !. Instru:nons for Precaranon of Data Entry begms m one report pened and ends m :nc$er. an entry should Sheets for Licensee Event Report (LER) File (NUREG41611.

be made for both report peneds to be sure all shutdowns usmg de following entiens:

or s:g:uncant power reducuens are reported.

TYPE. Lse "F" or "S" to indi ste either "For:ed" or " Sche.

duled." respe:n.eiy. for each sautdown or signi$ cant power B.

If not a :omeonent fadure, use the related commenent:

reduenon. Forced shutdowns include those required to be e.g.. wrong valve operated through error: !ist v2ive as minated by no later than the weekend following discovery component.

of an off. normal condition. It is re cgnized that some judg.

ment ts required in :stegorizmg shutdowns in this way. In C.

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

general. 2 for:ed shutdown is one that would not have been functien should be listed. The secuence of events.m:!ud.

completed in me absence of the :endition for which corrective ing de other components wh::h fall. should be desenbed acnon was taken.

under the Cause and Correenve Acnon to Prevent Recur.

rence column.

DURATION. Self. explanatory. When 2 shutdown extends Commonents that do not St any ex:stmg : ode snould be de.

beyond the end or 2 report penod. count only the tune to the

,j,33ted XXXXXX. The code 777777 should be used for end or the report penod and pick up the ensumg down time events wnere a component designation :s not spoti:2cle.

.n the following report penods. Report duration of outages rounced to the nearest tenth of an heur to fa:ditate summatien.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

l The sum of the total outage hours plus the hours the geners-RENCE. Use me :o!umn m a narranve fash:on to am;ufy or j

tot was on line should equal the 3ress hours in de report =g expiain de :ircumstances of de shutdown or power recuenon.

penod.

The :olumn shcuid me!ude the spectdc :suse for each mur.

down or stamn:2nt power reducnon and the immediate 2nd REASON. Categurtze hy :etter dewnauon m accordsnce centemoisted !cna term correenve senen taken. if sopropn.

j with the table aopearmg on the report form. If :stegory H 3,,

7us ciumn'should also ce used for a desenet:o' of the n

must be used.suopiy bnet eumments.

maior safety.related ;orre:nve mamtenance performed dunna StETHOD OF SHUTTING DOWN THE REACTOR OR

C"**I' C' E *"

d**"C" **NdiUg an : dent:0 canon of REDUCING POWER. Categonze ey nurneer desiansuun

'h'. '"""21 p2m 2enytty 2nd a re; rt at any smg:e re: case n, r2ctosetmty or smzie radiation execsure speculesdy ::ses:.

1%te that this differs trom the Edison Ele:tne Insutut, ated unh the out:ge wruca secounts for more tn;n 10 per;en:

TEED de6 muons of " Forced Parnal Outage" 2nc " Sche.

Of Me allC*2Cie annual v21J'5-l suied Partial Outm." For these tenna. EE! uses 4 hange or For long textual recorts eentinue narranve on seestate ; 2=er

.'O SIW as the break ;wnt. For larger power resetors. 30 5tw

.nu reteren.e tite shutdown or power re:u, nun foi w l

s tm imail a.hange to wanam espiananoo.

narrative.

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Docket No.: 50-315 Unit Names D. C. Cook Unit 1 Cmpleted Dy:

C. E. Murphy Telephone:

(616) 465-5901 Date: 6/8/83 Page:

1 of 2 b0tmlLY OPERATING ACTIVITIES - MAY 1983 Ilighlights:

The Unit operated at 100% power during this reporting period except for those periods of ti2ne when the Main Turbine Control Valves were tested.

These are addressed in the Sumnary.

A power reduction to 55% was started at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months on May 21 to repair an unisolatable steen leak on the West Main Feedptmp Turbine Steam lead drain piping. Repair to the Feedpump were cmpleted at 1450 hours0.0168 days 0.403 hours 0.0024 weeks 5.51725e-4 months on May 22 and the Unit was returned to 100% power at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months .

At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months on May 25 a power reduction was started in order to cmplete a surveillance test of the Steam Generator Stop Valves sinich was discovered to be overdue. The Unit was removed frm service at 1612 hours0.0187 days 0.448 hours 0.00267 weeks 6.13366e-4 months , the Steam Generator Stop Valves were successfully tested at 1636 hours0.0189 days 0.454 hours 0.00271 weeks 6.22498e-4 months , and the Unit was paralleled to the Systm Grid at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months . Reactor power was increased to 48% at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months on May 26 and was held there to allow the Delta Flux to cme back within the target band. At 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months on May 27 a power increase to 55% was started and this load was reached at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months . Power was held at 55% due to system load dmand. The Unit tripped at 0121 hours0.0014 days 0.0336 hours 2.000661e-4 weeks 4.60405e-5 months on Fby 28 when the " Power Ioad Unbalance" Circuit on the Turbine Generator was tested.

The Reactor was returno3 to criticality at 0153 hours0.00177 days 0.0425 hours 2.529762e-4 weeks 5.82165e-5 months on May 30 and the Unit was paralleled to the System Grid at 0419 hours0.00485 days 0.116 hours 6.92791e-4 weeks 1.594295e-4 months . At 1212 hours0.014 days 0.337 hours 0.002 weeks 4.61166e-4 months , due to system load d eand, the power increase was stopped at 58%. A power increase was again started at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on May 31 and 100% power was reached at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months .

An " Unusual Event" was declared at 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months on May 29 when the System dispatcher notified the Control Rocm operators that a Tornado Warning was in effect for the surrounding area. The Tornado. Warning and the Unusual Event was over at 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months .

The gross electrical generation for the nonth was 679,470 FMI.

Sunriary:

5/6/83 Reducing power to 95% at 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months for turbine valve testing.

Returned to 100% power at 0355 hoers on 5/7/83.

5/14/83 Reducing power to 95% at 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for turbine valve tecting.

Returned to 100% power at 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months .

5/19/83

'Ihe Containment Hydrogen Monitoring System was inoperable for a 10.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months pericd to repair a check valve.

5/21/83 Ecducing power to 55% at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months for repairs to the West Main Feedpump Turbine. Returned to 100% power at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months on 5/22/83.

Docket No.: 50-315 Unit Names D. C. Cook Unit 1 Cmpleted By:

C. E. Murphy Telephone:.(616) 465-5901 Date: 6/8/83 Page: 2 of 2 '

' 5/25/83 Removing Unit frm service at 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months for Steam Generator Stop Valve Surveillance. Returned to 55% power a 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months on 5/27/83.

5/28/83 Unit trip occurred at 0121 hours0.0014 days 0.0336 hours 2.000661e-4 weeks 4.60405e-5 months when " Power.Ioad Unbalance" circuit

.on the Turbine Generator was tested. Criticality was achieved at 0153 hours0.00177 days 0.0425 hours 2.529762e-4 weeks 5.82165e-5 months on 5/30/83 and the Unit was paralleled to the System Grid at 0419 hours0.00485 days 0.116 hours 6.92791e-4 weeks 1.594295e-4 months . Unit was returned to 100% power at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months on 5/31/83.

5/29/83

'Ihe West Motor Driven Auxiliary Feedpunp was inoperable for a 2.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period to replace faulty low suction pressure trip switches.

'Ihe Control Rocm 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 backup CO System remains operable.

2

't

i 1

DOCKET NO..

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 6-13-83 COMPLETED BY

.B. A. Svensson TELEPHONE (616)-465-5901 PAGE l of 1 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1983 M-1 The north waste gas compressor unloading valve, RRV-373, was

, leaking.by. Replaced the valve diaphragm and had the valve

-tested.

M-2 The seal water supply check valve for the hydrogen monitoring system, NS-262,'. leaked by during a waste gas leak test. Dis-assembled the valve, cleaned.and' checked the seating surfaces and reassembled the valve.

.M-3 The north waste gas compressor suction valve, RRV-375N, was leaking by.

Replaced the valve diaphragm.

C&I-l Gland seal steam exhaust flow recorder, SFR-201, failed low.

-The flow detector probe proved to be defective and was replaced.

The signal linearizer and voltage-to-current converter were re-calibrated. Recorder SFR-201 then operated correctly.

C&I-2 Ventilation system charcoal filter, 1-HV-ACRF-1, fire protection deluge valve would not open upon' initiation of actuating signals.

A defective printed circuit card in the valve control scheme was jumpered to allow testing of the deluge valve. The circuit card was then repaired and tested.

C&I-3 Ventilation system charcoal filter, 1-HV-ClPX, fire protection deluge valve would not open when tested. A temporary replace-ment actuation circuit card was installed to permit testing the valve.. The original card was then repaired, reinstalled and tested.

'C&I-4 High pressurizer pressure reactor trip protection set III bistable, PB-457 A/D, was' defective and required replacement..The replace-ment unit was calibrated and returned to service.

t-

_.. - - -. _ _..,, ~,.

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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 June 13, 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 May, 1983 is submitted.

Sincerely, vo /J. M /

W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

R. S. Hunter J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (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 1

ML20077A014

Text

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