Text

Monthly Operating Rept for Jan 1983
	ML20069A135
Person / Time
Site:	Cook
Issue date:	02/14/1983
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20069A114	List: ML20069A111; ML20069A135;
References
	NUDOCS 8303150544
	Download: ML20069A135 (11)
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.

CPERAT:NC DATA REPORT

..s..'

5D-316' DCC*

NO.

DATI 2-3-83 W.T. Gillett CO31?LITID SY TILI?ECNg 616-466-6901 O?? RAT!NG S ATUS DONALD C. COOK 2

Nor:s g, ung: 3,m..

2. Reporting ? :fod:

JANUARY 14A1 3411

3. t '~W Th --! Power p.tW:):

4. N::nepisi: R::i. ;(Crom StW ):

1133 1100

5. Design Ee=:i=1 R::in;(Nec 31We):

1118

6. Sf-Wu::: Dependsble Cay:d:7 (Cross 31We):

1082 T. Si=*- -m Dece=de.blee-- ci:f (Net 31We):

S. If Chan;es Ce= in C:pci:y R::i:;s (1::=s Nu=he 3 Th:ou;h 7) Since Las: Repor:. Give Reasons:

Item (3) licensed thermal power raised from 3391 (Mwt) to 3411 (Mwt)

9. b3cwer !.svel To Whi:h Res=: d,If Any (Ne: 31We):

10. Res==s For R-.::i:: ions.lf Asy:

" Itis 31onth Yr.<o. Data Cu=u!::ive 744 744 44.568

11. Hours != Repor.ia: P::fod

12. Number Cf Hoc:s R==orw s Cri:ir.1 266.5 266.5 31.079.9

13. Rec:or Rese ve Shu:down Hou:s 0

0 0

14. Hours Genemu2r Cn L'==

186.8 196.8 10_14R.6

15. Uni: R. serve Shutdown Ho=:

0 0

0 l

16. Cross The:=:1 E::: ;y Cen:=: d (3:WH) 341 514 341.514 og.gnq.765 103.570 103.520 31,061.090

17. Cross IIe==i=l E=er;y Cent::::d G.tWH1

13. Nc: EIe==f=1In :;y Gene =::d C.;WE) 97,163 97,163 29.936.955 25.1 25.1 72.1

19. Uni Servi== ?:ctor F

25.I 25.1 72.1

20. Uni Av:iIshill:7 :c:or 12.1-12.1 67.2

21. Uni: C: sci:7 F:::=r(Usi=; MDC Nee) 11.9 11.9 66.8

22. Unit C:escity. :::or (Using DIK.4et) 12.3 12.3 14.0

'3. Uni: For::d Ou::ge Race

24. ShutdowTts Scheduled Over Nec 5.itor::hs (Type. D:te.:nd Du:::: ion of I:ch1:

25. If Shu: Down A: End Of Report Period. Isti=::ed D:re of S:::: p:

. 25^ Units In Tes: S::::s (?:for ta Ce==e :is! Ope =:fo:. :

Forees:

Achieved INITIA L CRIT'CA LITY

~

INITIAL I*.ICTR:CI Y CO.*4.'.:IRC:A' 0?ER.GCN

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8303150544 830214 fj PDR ADOCK 05000316 R

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-316 UNIT 2

DATE 2-3-83 COMPLETED BY W.T. Gillett TELEPHONE 616-465-5901-MONTH January 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1

2

=

18 3

19 4

20 5

21

~

6 22

~

7 23 291 8

24 457 9

25 459 10 25 472 11 27 94 12 28 194 13 29 634 14 30 685

~

15 31 759 16

~

i INSTRUCTIONS

\\ \\-

On this fonnat list the average daily unit power level in MWe-Net for each day in the reporting month. Ccmoute to the nearest whole megawatt.

I k'

N.

lj C

ook - Unit 2 IJNil'Silu'llHlWNS AND POWiiH HliDUrI'lONS DA lli 2-14-83 i

COktri.lilliD liy B.A. Svensson Hi.POHI AIONill January. 1983

.t iil.l:rilONii 616-465-5901 PAGE 1 of 2

't I icensce 5 e.,

5 3E

'h 2 EI 9

cause a c nscaive N' '.

D sle Q

is @

.2 s $

livent si y

$3 Ai ns ui s..

g$3 j En g Hepoil #

'E O Psevens Hecussente H

6 i

119 821121 S

531.1 B&C 1

N.A.

ZZ ZZZZZZ The unit was removed from service at 0127 on 821121 for scheduled Cycle III - IV refueling and maintenance 3

outage. Low power physics testing was performed on 830120 thru 830122 and the unit was returned to service at 0304 hours0.00352 days 0.0844 hours 5.026455e-4 weeks 1.15672e-4 months on 830123. Total length of the outage was 1513.6 i

hours.

120 830127 F

18.1 G

3 N.A.

ZZ ZZZZZZ Unit tripped from 60% power due to operator error. Operator manipu-lated turbine reset switch rather than the turbine operating device control switch when increasing tur-bine load. Cause of trip was low level coincident with steam / feed-water mismatch on No. 23 steam gen-erator. The unit was returned to service the same day.

I 2

3

.I 12 I nsceil Iteason:

kletiniil:

1:xinins G - Instaursions S: Silicalnical A l'qmpmes. 1 anime (1.n plain) 1 klanual fin Psepasatuni of lial.

ll klaintenance ni Test 2 klannat Saam.

linsey Sliceis foi iicensee e Refncling I-Automatic & sam.

liven Repini (I l'lt ) I ale (NilHI G-D Regulatoay itesesidion 1-Othes (lixplani) 0161) l' Opesatus l~s.ainsng & lircuse 1 xamination 5

I;- Ailnunist sative I sinlisi i Same Somce G Opciational I.isos ilhplatul P8///)

ll Ollies (lixplain n

UNIT SHUTDOWNS AND POWER REDUCTIONS LNSTRUCTIONS This report snculd desenbe 211 plant shutdowns dunn; te m n: rdan: wi6 de ta:ie 2peestmg on de report form.

report penoc. In addition. It should be the sour:e of explan.

If :stegory a must be used. suppiy bneic:mments.

stion of sigmdcant dips :n ave:2ge power levels. Ea:h sizm.

LICENSEE EVENT REPORT =. Referen:e de app!:nbie ii: ant redu:non m pcwer level (pester dan '0" reducticn m average daily power level for the preceding 24 houn) re.enme oc:unence pensam; to se ' autsge or power acu:nen.

mer de S-n : cur pans (ewn yes. sequent:1 could be noted, even though te umt may not have been saut down ecmplete!y1 ~or such reductens a power '. eve!.

repcrt num er. o:::: ence ::de 2nd re: ort type) or tne nye me durst:on should ce 'isted as zero, the medod of reducucn part des:;nat:en as :es:n=ed ;n item i, or Instruenons tar should be listed as 4 (Other). 2nd de Cause and Cor:eenve Paparanon of Dats Entry Sheets for L::ensee Event Repen A hen to Prevent Re:unence :clumn shotdd ex; ism. The tLER) File (NUREG-0161). Tis tnformanon may not be Cause 2nd Corre::ve Acnon to Prevent Recunence eciumn

mmetate:y evident tor 211 such shutdowns. of :cune, smee should be used to provide any needed explanation to fully turther mvestgation may be requ: red to ascertam *hetner er desence the cir:umstances of de outage er power reduction.

not 2 reportsele oc:urrence was mvolved.) !. de outage or power re:ucnon wdl not result in 2 reports:le oc:urrence.

NUMBER. This : iumn should indi::te the secuential num-the pos:tive mdicanon of th:s !:ck of ;ctre!st:en should te bet ass:gned to each shutdown or ugruilcant redue' tion:n power noted as not applic:c:e (Ni A).

for mat esiendar year. When a shutdown or s:gmd: ant power SYSTEM CODE. The system in whid the outan or :cwer reduenon begms in one report period 2nd ends m another.

redu non anpnsted should,se notec sv de two dig:t eede of an ent:v. snould be mace for both report penods to be sure cxmbit G. Instrucuens tor Preparsuon of Data,. catty snetts tnt 3 2 utut.i.,s 1.G.y.a. as. power reducuons are reponed.

for Lcense Ennt Recon R,=R).. (NL. REC 4!61).

sil snutdowns or stamncant rue n,t cw 4.

..ition..,.o.......

..r ber should be assip:ed to esen entry.

Systems mat do not fit 2ny exisung code shouic :e dengna.

ted XX. The :oce ZZ should be used for dose events wnere DATE. This column should =dicate the date of de start 2 system is not app;i: sole, of each shutdown or ugmd: ant power reduenon. Report as year, menth. 2nd say. August 14.1977 would be reponed COMPONENT CODE. Seis:t de most 2;pecpnate ;omponent as ~70514. When 2 shutdown or s:gmficant power reducten from Exiubit I Instru:nons for P: =2: anon of Data Enta beg:ns m ene report pened and ends m ancier, an entry should Sheets for Licensee Event Report (LER) Fde (NUREG4161).

be made for both report pencds to be sure all shutdowns using the followmg :ntiena:

or sipuncant power reduchons are reported.

TYPE. Lse -F" or "S" to indicate e:ther"For: d" or " Sche.

duled." respe:hvely, for each shutdown or signincant pcwer B.

If not a : m enent fadure, use the reisted ecm:enent.

reducaon. Forced shutdowns in:iude those required to be e.z.. wrong valve operated through erron !!st valve as mitiated by no later than the weekend following dis:cvery enmoonent.

of an off. normal condinon. It is re: gm:ed that some judg.

~

ment :s required in :stegonz=g shutdowns in this way. In C.

If a cham of failures oc:urs. the dnt ecmeccent to m:i.

general. 2 for:ed snutdown is one that would not have been function should be listed. The secuence of' events.melud.

compicted in the absen:e of me condit:en for which correcuve ing de other : mponents wh::h fail. snould be des:nbed acucn was taken.

under the Cause and Corre:nve Acuan to P: event Recur.

rence column.

DURATION. Self. explanatory. When 2 shutdown extends Components that do not de any ex:stmg : ode sn.ouid.:e de.

beyond the end or. 2 report pened. count only the ttme to the signated XXXXXX. The code Z.,.ZZs2 shouid.:e used for t

end or. he re: ort penod 2nd icA, un the ensumg down t=:e in de tod.owmg report :eneds. Report duranen of cutages

.aes:ctat:ca is not spou:scle.

events where a comecnent rounced to tne nearest tenth of an hout to facditate summst:en.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-the sum of the total autage hours plus the hours the gener2 RENCr. se the eclumn in a narrat:ve fasPaan to 2mpitfy or tor was on line should equal the pcss hours in the reportma expisin de ::rcumstances of de shutdown or power recu:non.

pe ned.

The eclumn snculd include the spectdc :suse for each shut.

down or sismde:nt power reduenen and the immediate anc

-. tter demnanon in accordance REASON. Catezor:ee by

.e eentemetated long term corre:nve acucn taken, if sp roen.

with the racie 2 pearms un me re:urt form. If :stegorv H ims ;mumn snould also be used,.or a desenetion at tne ste.

must be used.su p.iv bner. eumments, maict safety.rei:te. :orreenve mamtenance pertormec dur:na a

the utage or p wer reduenen me!uding an : denude: tion of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER. Catezonze ey numcer destznsuun

{ ;nne:1 pst. 2enmy and a repen at any nnte.mase n r:ctosenytty or smpe tsdist:cn ex:csure spes:desily assee:.

1%te that th:s differs from the Edison Ele tn: Instnute atec wnh the out:ge wrach seecunts for more tnan 10 per;en:

TEED dedruncns of " Forced P2rtul Outage" 2nd "Sene.

olde 2ilo*3cic 2nnual v21ues.

duied Partial Ouac ' For these termi. eel uses a shange or For long textual recons eent=ue nar:2nve on se:2r:te ; 2:er

.0 MW 25 the =ren ;wnt. For targer puwer reactors.30 MW

.nd reteren e the shurcown or power :::u nun im a

's rm >mJll J.hante to warGut MplJnJHoH.

n3rr3UVe.

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50-316 I

N

-0.C Cook - Unit 2 llNITSiltilDOWNS AND l'OWI'it RiiDLICTIONS T-Td-83 DAug COhlPl.linip HY

.B.A. Svensson ut:ronI hlONill January,1983 616-465-5901

.Ilit.lfHONii PAGE 2 of 2

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g <3 ranse a concciive t

Aon.ni no No.

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s 2s5 I!vens 3,y

{a.O Psevent Rccinscoce y3 y

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Q 1,

1 21 830128 F

8.0 H

1 N.A.

ZZ ZZZZZZ The unit was removed from service to perform a modification to the turbine speed governor. The speed governor installed during the outage on 830127 prevented the unit load from being increased above 38% power.

The unit was returned to service the same day. 100% reactor power was reached for the first time in Cycle IV at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months on 830202.

1 I

J

.1 4

1 ; l'oeccal Itcason:

hicalniil:

1:xinine G - In.tnictions S: Llicilnical A 1 Inspmes.: 1 ailine (1.xplain)

I h1anual los Paciusainni of D.ita Il klainten ence or Teil 2 klannat Sciain.

I:niay Slicess foi I i.cence r Itefneling

.1 Antonweie Stsam.

liven ReposI (I l'It ) File INilHI G-In Regulainiy itestnction

-l Oilies (lixplain) 0161) i Opesalos liaming & I secuse 1.xamin.stion l' Ailmiinst r ative 5

G Opelational I.nus IF xplain) 1: slaih:11 S.nne Sunce es///)

ll Ollies (lisplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS LNSTRUCTIONS This repon snould des;n:e 211 ;!1nt shutdowns dunng te. m m=rdan;e At:h de ts:!e ap canng on the repor fccm.

report pened. L. 2ddition. it should be the sour:e of expl:n-If category 4 must be used. supply bnef =mmen:s.

suon of sigruncan: dips a 2verage power leveis. E2d nzn:.

n: ant redu:non m pcwer level (pester dan 2M redue:Icn LICENSEE EVENT REPORT :. Reference e appitmble m average dany power leve! for :ne preceding 24 hnurs) repor:2cle oc:urrence penammg to de ou:2ge or, power I'0 2*C :nter e :.:s: : cur pans (event yes:. sequent:a could be noted, even mough te umt may not have been MC' 200 f 890ft :YF8) Of 38 UV8 snut down completely. For suca reducnons in power '.evel f 70ft nUC *f 400;ft nC l

trie durst:on should be !!s:ed as zero, the medod of reducucn pan,enpauca as :esen ed m Item !, or Ins::uenons f;r Pre:2rauen of Data Entry Sheets for L ensee Event Reper:

should be lis:ed as 4 (Other). 2nd de Cause and Cor:eenve Acucn to Prevent Recurrence ;Olumn should expiam. The tLER) File (NUREG.0161). Th:s infor=2non =2y not :e Cause md Corre:nve Acnon to Prevent Recur:en:e eciumn mmediately evident for 2i1 such shutdowns, of coune. smce should be used to provide any nee:ied explanation to fully rurther :nvest:gaden may be requ: red to ascertam whetner or not a reportsbfe oc:urrence was involvec.) If the cutage or descn' e the ::r:umstances of the outage er power reduction.

c power reducten wtil not result in a repons:le oc=tren:e.

NU31BER. T'us :olurna should india:e the secuential num.

the postave mdica:icn of $1s lack ci ;orreianon should te noted as not appnedie GA).

ber assiped to eacn shutdown or sigmdcant reduction m power for : hat calendar year. When 2 shutdown or s:gmncant power SYSTE31 CODE. The, system :n wh:2 the outage or pcwer reduenon begms m one report pened and ends m another.

reduenon ongmated diould be acted :y the two i.g:t ecce at.

an entrv snouL, be made for,s,otn re:or: penods to be sure

=xment G. Instrucacas for Pre;2:2non of D2:2 Entry snee:s a

.il snutdowns or sta:uncant power reduedons are repor:e.

t r bcensee vem Re:on RER)._n,e M. REG-W Unt:12 urut has 2:15eved its first powe generation, no num-bet should be assiped to es:h entry.

Systems that do not fit any existmg : de shouic :e deszp3-ted XX. The :oce ZZ Aould be used fcr $ose events where DATE. This column should mdicate de date on the s:2rt 2 system is not appli:2 ele.

of each shutdown or sigmn:2nt power redueden Report

.s year. =cnth. 2nd day. Aupst 14.10~7 would b/ reported COSIPONENT CODE. Seie:: de mos: 2;prepna:e ;cmponent as 7 0514. When a shu:down or sigmficant power reducnon nom Exhstt I Ins::u:nons for P:e:2:2nen of Data Ent:5 begms m one report penod and ends m another. 2n entry should Sheets for Licensee Event Report (LER) Fde (NCREG.0161 L be made for both report peneds to be sure all snutdowns usmg de followmg cntiens:

or sig:uncant power reduencns are reported.

TYPE. Use "F" or "S" to indicate either "For: d" or " Sche.

duled." respeenveiy, for each sha:down or signid:2nt power B.

If not a :cmeonent failure, use de reisted ;cm;cnent:

reducnon. Forced shutdowns meiude dose requtred :o be e.g.. wrong v21ve operated throup error: !!s: valve as mitiated by no later than the weekend following discovery component.

of an off. normal condition. It is reccg.:2ed that some judg.

ment is required in :stegonzmg shutdowns in th:s way. In C.

If 2 cham of fattures occurs. the Ers: cemconent :o mai.

general. 2 for:ed shutdown is one that would not have been function should be listed. The secuence of'even:s.mciud.

completed in de absence of:he =ndition for w hich corre:dve ing the other components which fail. snould be des:nbed 2cuan was t2 Ken.

under the Cause and Correenve Acnon to P: event Recur.

rence column.

DURATION. Seif. explanatory. When 2 shutdown extends Comeonents that do not St any ex:stmg : ode sn.ou;d.ce de.

beyond the end at 2 report penod. count only the ume to the uM RER h2 M MhMa and of.the re: ort renod 2nd :u un the ensumg down tt=e m the rei:owing report pencds. Report duranon of outages des:.ananon is no: spen:2 le.

events where 2 com onent rounded to the nearest tenth of an hout to fac:litate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

ahe sum of tne total outage hours plus the hours the gene:2

, Ce.

.se me column in 2 narranve fash:on :o ampiify or tot was on Im.e should equal the gress hours in the repornna exclam the circumstances of the shutdown or ower recucnon.

-e of-The : lur.n snculd indade the spe::d: :ause for each shut.

r'"

down or sizmilcant pcwer reducncn 2nd the immediate 2cc REASON. Catesonze 5s,etter w,ennation in accordance c:ntemolated !cng term correenve 2:nen taken, if appro:n.

- i with the tacie 2=pearmg on tne report form. If :stegorv H ste. ams ctumn should also :e used :.or 2 descn= tion of:ne must ' e used supoiy br:et eumments.

maior safety reisted orie:nve mamtenance per:or:nec dunna the outate or power recucnon inc!udinz 2n identt0c2 tion of StETHOD OF SHUTTING DOWN THE REACTOR OR the ent:est p2:n 2envity and a report at any smile reiesse f REDUCING POWER. Categonze ey numner des:panun r2diosenvuy or smile radisticn ex:osure spee:Sc2ily assec:.

l%te that this differs trom the Edison EIe :n: Insutute sted with the outsae wruch secounts for more tnan 10 percen:

t EEI) detirunons of " Forced P2rnal Outage" 2nc "Sene.

oide 2ilow20 e 2nnual v21ues.

auted P2rtial Out2p

For these tenn>. EE! uses a shange ut For long textusi re: orts e ntmue n2: 2nve on se:2rste p2:er 10 31W as the creak ynt. For larger power resetors.30 5tw

.nd reteren e the shutdown or power recu nun foi w

.s tm smail 2.hange to wariant espianation.

narranve.

(oi--

l

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_.___m_

Docket No.:

50-316 Unit Name:

D. C Cook Unit 2 Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date: 2/11/83 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - JANUARY 1983 Highlights:

The Unit entered this reporting period in the Refueling Mode (6).

The Unit had been shutdown at 0127 hours0.00147 days 0.0353 hours 2.099868e-4 weeks 4.83235e-5 months on November 21, 1982 for it's third Refueling Outage.

The Unit was returned to the "In Service" operating condition during the reporting period.

Details of this follows in the Summary.

Total electrical generation for the month was 103,520 MWH.

Summary:

The Reactor Plant entered Mode 5 at 1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months January 4, when initial tensioning of Reactor Vessel Head Studs was initiated.

Filling and venting of the Reactor Coolant System was initiated at 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months January 9, and was completed at 1757 hours0.0203 days 0.488 hours 0.00291 weeks 6.685385e-4 months January 12.

Heatup of the Reactor Coolant System was initiated at 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months January 15 with entry into Mode 4 being made at 0644 hours0.00745 days 0.179 hours 0.00106 weeks 2.45042e-4 months the same day. Entry into Mode 3 was made at 1608 hours0.0186 days 0.447 hours 0.00266 weeks 6.11844e-4 months January 16 and normal no load temperature and pressure was obtained at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months January 17.

With all control rods fully withdrawn, except for Control Band "D" which was positioned at 205 steps, the Reactor Coolant System Boron Content was diluted to 1700 PPM over a 7h hour period starting at 2137 hours0.0247 days 0.594 hours 0.00353 weeks 8.131285e-4 months January 18.

Dilution to criticality was initiated at 0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months January 20 and criticality was obtained at 0828 hours0.00958 days 0.23 hours 0.00137 weeks 3.15054e-4 months the same day. Critical Boron Concentration was 1448 PPM.

Low Power Physics Testing was interupted at 1942 hours0.0225 days 0.539 hours 0.00321 weeks 7.38931e-4 months January 20 when the Reactor tripped due to Lo Lo Level in #22 Steam Generator.

The Reactor was returned to criticality at 2222 hours0.0257 days 0.617 hours 0.00367 weeks 8.45471e-4 months the same day.

Low Power Physics Testing was completed January 22 and Reactor Power was increased to greater than 5% at 1659 hours0.0192 days 0.461 hours 0.00274 weeks 6.312495e-4 months in preparation of rolling the Turbine / Generation unit.

The Main Turbine was rolled at 1754 hours0.0203 days 0.487 hours 0.0029 weeks 6.67397e-4 months January 22 for Overspeed Trip Testing. The Unit was shut down and placed on turning gear when the Overspeed Trip Devices failed to fuction at the expected speed.

Inspection of the Overspeed Trip Devices found some fretting type wear along with a varnish type deposit. The Overspeed Trip Devices were replaced and the Main Turbine was rolled at 0034 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months January 23 and Overspeed Trip Tests were successfully completed.

Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 i

Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date:

2/11/83 Page:

2 of 2 The Unit was placed in parallel with the system at 0304 hours0.00352 days 0.0844 hours 5.026455e-4 weeks 1.15672e-4 months January 23 and loaded to 30% power by 0405 hours0.00469 days 0.113 hours 6.696429e-4 weeks 1.541025e-4 months the same day.

t The Unit was loaded to 35% power over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp starting at 0515 hours0.00596 days 0.143 hours 8.515212e-4 weeks 1.959575e-4 months January 23.

The Unit was loaded to 48% power over a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ramp starting at 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months January 23.

Unit loading was initiated at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months January 27 at the rate of 3% per hour. At 0419 the Unit tripped from 60% power when an incorrect control switch was operated. At the time of this trip control rod H-8 indicated that it failed to insert, the last 25 steps, into the core.

Emergency Boration was used to cover this indicated deficiency.

Postion indication of rod H-8 slowly decayed to zero. This is a reoccurring problem with this particular control rod position indication.

The Reactor was returned to criticality at 1442 hours0.0167 days 0.401 hours 0.00238 weeks 5.48681e-4 months with turbine roll at 2105 hours0.0244 days 0.585 hours 0.00348 weeks 8.009525e-4 months and the Unit paralleled to the system at 2225 hours0.0258 days 0.618 hours 0.00368 weeks 8.466125e-4 months January 27.

The Unit was loaded to 38% power by 0145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months January 28. The 38%

was maximum loading that turbine controls would allow.

During the outage of January 27, the Operating Device (Governor) of the Main Turbine had been replaced due to the previous one being somewhat erratic, when used to control unit output.

The Turbine / Generation Unit was shut down over a 1k hour ramp starting at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months January 28. The Reactor remained critical at less than 10% power.

Inspection of the new Operating Device found an internal plug that should have been removed prior to installation. This plug was removed and the Unit was rolled at 1940 hours0.0225 days 0.539 hours 0.00321 weeks 7.3817e-4 months and paralleled to the system at 2154 hours0.0249 days 0.598 hours 0.00356 weeks 8.19597e-4 months .

The Unit was loaded to 68% power by 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months January 29.

The Unit was loaded to 80% power over a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ramp starting at 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months January 31 and remained at that level for the remainder of the reporting period.

The West Component Cooling Water System was inoperable for a 9k hour 2

period January 26 for testing of a system safety valve.

The AB Diesel Generator was -inoperable for a 16b, hour period January 26 for replacement of an exhaust system expansion joint.

UNIT NAME D. C. Cook - Unit No. 2 DATE 2-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 3 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1983 M-1 SI-125, isolation valve on the one inch boron injection tank bypass line was leaking. Replaced the valve stem and disc assembly. Lapped the valve seat.

M-2 Pressurizer power operated relief valve, NRV-151, was leaking by. Replaced the valve seat, plug, stem, stem pin and gaskets.

Reassembled valve and had it tested.

M-3 Component cooling water containment isolation valve, CCW-135, failed to pass the type C leak rate test. Replaced the shaft and disc springs and lapped the discs. Had the valve retested.

M-4 Boron injection tank discharge isolation valve to loop 1, IMO-51, motor operator housing was broken. Replaced the housing and the bevel gear cover. Reset and tested valve.

M-5 Containment spray check valve, RH-142, was leaking by. Dis-assembled valve, cleaned and lapped seat. Reassembled and had valve retested.

H-6 Safety injection pump discharge crosstie valve, IM0-270, would not open. The operator motor had a fault. Replaced the motor and had the valve tested.

M-7 A weld leak developed at the branch connection for the pressure instrument on the discharge of the East containment spray pump, IPI-210. The leak was from a crack in the weld. The weld was ground out and rewelded. A second leak developed in the same instrument line downstream of the root valve. The tubing was l

cut off and rewelded. Necessary NDE was completed.

M-8 Pressurizer spray control valve, NRV-164, was leaking by. Re-placed the valve internals and had the valve tested.

M-9 Boric acid blender outlet valve, PW-265, was leaking. Replaced the valve body, stem, compressor and diaphragm.

M-10 The controlled leakage seals on No. 22 reactor coolant pump were inspected. Replaced No.1 seal insert, No. 2 seal ring, runner and housing and No. 3 seal ring.

M-ll Isolation valves, CCW-243-72 and CCW-244-72, for component cool-ing water to penetration cooling coils failed to meet type C leak test criteria. Cleaned the valve internals and lapped the seat and plug. Had the valve retested.

UNIT NAME D. C. Cook - Unit No. 2 DATE 2-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 3 MAJOR SAFETY-RELATED MAINTENANCE JANUARY,1983 M-12 The inlet check valve to the regenerative heat exchanger, CS-321, failed to meet the type C leak rate test criteria. Lapped the valve disc and the faces of the disc hanger bushings. Replaced the bonnet gasket and had valve retested.

M-13 Letdown isolation valve, QRV-ll2, hed an air leak from the air operator. Replaced the operator diaphragm and had the valve testede M-14 Safety valves, SV-1. and SV-2, for No. 21 steam generator were leaking by. Replaced the valve discs, cleaned and lapped the seats and replaced the flange gaskets. Tested both valves and found setpoints acceptable.

M-15 Due to a problem identified in Unit 1, the bonnets of main feed-water check valves, FW-ll8-1, 2, 3 and 4 were removed to check for wall thinning at the bottom of bolt holes in the valve bodies. No significant wall thinning was evident, but the body wall was built up by welding as a precautionary measure. The necessary NDE was performed and the valves were leak tested at operating pressure.

M-16 Accumulator fill valves, IRV-121 and 131, were leaking by.

Lapped the plug and seat in IRV-131. Replaced the internals in IRV-121. ilad both valves tested.

H-17 No. 3 steam generator stop valve dump valve, MRV-232, was leaking by. Replaced the valve stem, plug, seat ring, cage, and gaskets.

Had the valve tested.

M-18 The exhaust expansion joint on AB emergency diesel was leaking.

Replaced the expansion joint.

C&I-1 Lower containment 4rea monitor, ERS-2302, was counting erratically.

The detector was replaced to restore proper operation to the mon-itor.

C&I-2 Residual heat removal heat exchanger "W", outlet valve IRV-320 failed open, due to a control air line which had become detached.

Investigation disclosed that vibration had caused a connector to break. The connector was replaced and the valve was tested satisfactorily.

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UNIT NAME D. C. Cook - Unit No. 2 DATE 2-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 3 of 3 MAJOR SAFETY-RELATED MAINTENANCE JANUARY,1983 C&I-3 During the performance of a control room power load conservation surveillance test, relay 5 X l-T21B would not trip train "B" battery charger to the "N" train battery. A defective relay, 88X1BCB, was replaced to provide correct trip.of the charger.

C&I-4 Steam generator No. 3 stop valve, MRV-230, would not open due to non-closure of its hydraulic bypass valve. A broken wire on solenoid 20-3SG3H(S3) was identified and repaired, after which, operation of the solenoid was verified.

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ML20069A135

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