ML20072C423

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Monthly Operating Rept for Dec 1982
ML20072C423
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/13/1983
From: Might A, Murphy C, Svensson B
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20072C406 List:
References
NUDOCS 8303080429
Download: ML20072C423 (9)


Text

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OPER.CINC DATA REPORT

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5'0-315 DCC:cT NO.

DATI 1/4/83 A. Minht

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CO>t?LETIO ?.Y (616146ci_sq01 TELI?HCyg O?IhT!NG s'"ATUR Donald C. Cook 1

Not:s

1. Uni:Nsese:

December 1982

2. Repor.:n;?c:fod:

3250

3. LkensedTh -'?:wcr(MW:):

~

1089

4. Pismephte F.=in;(Cross MWe):

1054 S. Design Ile=:i=1 R=in;(Nec Sih e):

1080

6. 5 % un: Depend:ble Capsci:7 (Gross MWe):

1044 T. Sime--m De: --d '!: r._.=i:.f (N c yw,):

S. If t -- ;es Oc_.::in Capsci:7 R=in;s (1: =s Numbe:3 Th.ough 7) Sinc = L:s Repor:. Give Renons:

9. ?ower Level To Whi=h Kes=i==d.If Any (Net Mwe):
10. Re: sons For R==hdons.If.uy:

This Month

' Y.<o. Casa Ca. :u!=ive 744 8.760 70.128

11. Hours != Repor.in; ?e:iod 744 5,608.4 51,881.6
12. Nu=her of Hou:s R==:=r Wu C i:i::1 463
13. Re:c:or Rese:ve Shu:down Ho==

744 5.490.7 50.712.9

14. Hours Ce==r_-:=r On.LS,
15. Uni: R:scrve Shutdown Ec::=

321 2.180.316 16.940.371 147.302.560

16. Cross The:=.I E==;y Cen==:ed (MWH) 712.670 5.554,070 48.435.850
17. Cross IIe=ri=!Ine:;y Cen----I p.tWH) 685.367 5.352.823 46.593.501
13. Net IIe=:i=1 E==:;y Cenen:ed C.;W~~)

100 62.7 74.5

19. Unit Serri = F:=sr 100 62.7 74.5 l
20. Uni: Ar Ihhi!I:y F:c:or 88.2.

58.5 67.3

21. Uni: C:: sci:/ 7:c:=r (Usin; MDC Net) 87.4 58.0 64.1
22. Unit Cassdty. :cor (Using DER.iets 0

20.7 8.5

23. Uni: Forced Cu::ge Rat,
24. Sh : downs Scheduled Over Nex: 5 Mon:i:s (Type. 0:te.:nd Du=:fon a(I:cht:

4

15. If Sht: Down At End Of Report Period. I:ti==:ed D:ce of Star::p:

.25; Unics in Tes: S;:::s (Pnor to Ce==e =is! Ope =:foni:

Foreest Achieved l

INITIA L CRIT;CALITY

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INITIA L II.ZCTR:C*W Co.tMI?.C:A: 0?E7..G;CN I

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8303080429 830113 PDR ADOCK 05000315 R

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'q3; 3 AVERAGE DAILY UNET POWER LEVEL 00CKET NO.

50-315 UNIT 1

DATE 1/4/83 COMPLETED BY A. Might TELEPHONE (616)46d 5901-MONTH Decembe'r 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 565 17 1029 2

564 18 1030 3

525 19 1033 4

838 20 1032 5

1034 21 1032 6

1031 22 891-7 1032 23 540 8

1031 24 678

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9 1032

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25 864 10 1029 25 560 11 1028 27 878 12 1029 28 1032 1030 13 29 1032 s

14 1030 30 1032 15 1032 31 1030 t

1033 INSTRUCTIONS I

l On this format list the average daily unit power level in MWe-Net for each i

day in the reporting month. Comcute to the nearest whole megawatt.

l.

I I N UNIISilU'lDOWNS AND l'OWi:lt ItliplirTIONS An if C

ook - Unit 1 DA~Ili _l-13-83 COklel.E liip liy B A. Svensson IlliPolt I klONill December,1982 int.tpliONE 616-465-5901 PAGE 1 of 2 i

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'h Iicensee E s..

9 ranse & concuive H...

p.n e g,

Hg 5

.2 g &

livens a 'g Aui.ni in l

55g ItcpusI #

iE U b'

Psevent 1(ccnnenie P

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a 189 821129 F

0 A

4 N.A.

CH PUMPXX Reactor power was reduced to 53% on 821129 to remve the east main feed-pump turbine from service due to ex-cessive vibration-Investigation re-vealea that the coupling sleeve on the turbine half of the coupling was cracked the length of the sleeve. A i

complete new coupling was installed.

During the return to full power on i

i 821203, a steam leak developed at i

62% power on a test line on the main i

steam lead, down stream of the No. 3 turbine control value. To repair the l'

steam leak a power reduction to 30%

was required. The leak was repaired and the reactor power returned to 100% power on 821204.

190 821222 F

0 A

4 N.A.

CH PUMPXX Reactor power reduced to 55% to re-move the west main feedpump from i

J 3

-4 1: l'os ceil iteason:

klethoil:

1:ntnint G Insinictions

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S. Se lectf ulcal A liinipanes.: l ailuie (l.mplain) 1 hlannal los Pacpasasion ol para 11 kl.iinicnance or Test

! klannal Scsani.

linisy Sheels nu 1.icemce C Itcl'ncling

1. Antoin.asic So. ens; I vent Itepos t il l'lO 1 ile INllitt G-In Itegulatoiy itesisicsson

-l Othes ll.nplain) 0161) l' Opesatos I's.r'ning & Iitense 1.naniination 12 Asinunisisative 5

G Opesarional 1.noe Iliplain) lainhet i Saine Sonice ps///)

11 Olhesdi:spl.iint

UNIT SHUTDOWNS AND POWER REDUCTIONS a

INSTRUCTIONS This report snould desente all piant shutdowns dunng ne

n: rdance w:th de ts:le 2= esnng on me report form.

report pened. In 2ddinon,it should be the sour:e of expian-If category 4 must be used. sup;iy bnef::mments.

suon of sigmecant dips :n average power :evels. E2d upt-LICENSEE EVE.NT REPORT =. Reference me app'::bie d

d: ant reduenon u: power !evel (pester dan 209 reduction

n average daily power level for the preceding 24 hnurs) reperu:le cc:ur ence pensming to se outage or power eeu:nen. :nur e 5-n :our pans (ennt year. sequennn should be noted, even icuzh de amt may not have been snut down completely. For'such reducnons in power ' eve!.

report numcer. a::urren:e ::de and report type) of me dve l

the durst:on should ce '.isted as zero. de medod citedu:non par *. designation as des:nbed in [ tem 17 of Instruenons f:r snould be 'dsted as a tother). 2nd $e Cause 2nd Corree :ve Pre =aranon of Dats Entry Sheets for L:censee Event Re:crt A:tien to Prevent Re:urrence :clumn should ex:!ain. The (LER) File (NCREG.0161). T'as informanon may r:ct be Cause 2nd C:rreenve Acnon to Prevent Recurrence coiurnn immediately evident for all such shutdowns. of course, s. e should be used to provide any needed explanation to fully tuttner.nvesngation may be recu: red to ascertam whetner er desence the ;ircumstances of the cutage or power reduchen.

not 2 repor:2cle oc:urrence was involved.) If the outsge or power reducnon wtli not result in a reportable oc:urrence.

NU3tBER. This ciumn should ind!=te the secuential nu=.

th' P052nve mdi:stien of is !sck of correistion should te ber assigned to each shutdown or signidcant reduenon m power noted as not applic:bie IN, A).

for mat c21endar year. When a shutdown or s:;md:2nt power SYSTE31 CODE. The system in whic: the outsp or power reduetton begins m one report pened sad ends :n 2nother.

reduction ort; mated should be noted oy the tw'o t.;:t ecce at.

an entrv shouL., be mace for botn recon penods to be sure

'***** C ' IU5""4UO"5 f0' Inparsuon oi Data Entry snees Unts a urut "s 2.A.u.v.. .s ^ power redu: dons are reported.

sil snutdowns or stemd: ant for Ucensee Ennt Re=on (L:.R) ru,e (NL, REG.0161).

s.

.. st.ow

j..cratioa. no...

ber snould be assiped to e2en entry.

Syste=s that do not fir any existmg : ode shouic :e des:ps.

ted.11 The :cce Z2 should be used for $ose events where DATE. Utis column should mdicate the date of the start a system is not appd:2 ole.

of e3Ch shutdown or 512md:2nt power reducuan. Report as year. mcnth. 2nd day. August 14.1o 7 would be reported C05tPONENT CODE. Se; :t de most 2;ptcpriate arnpunent as 770514 When a shutdown or sigmdunt power reducnen from Exhibit I. Instruchons for Preparanen of Data Entr>

begms m one report pened 2nd ends m anomer, an entry should Sheets for Licensee Event Report (LER) Fde (NCREG.01611.

be mace for both report pencds to be sure 211 shutdowns using de following entiena:

or sigsd ant power redu: hens are reported.

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

Juled." resce:nvely, for each shutdown or signincant power B.

If not a co toonent failure, use de reisted ;om enent reducnon. Forced shutdowns indade dose required to be e.g.. wrons valve operated through er or: list valve as

nitisted by no later than the weekend fo!!owing discovery comconent.

of an off. normal :endit:on. It is recogni:ed that some judg.

ment is requved in :stegenzmg shutdowns in th:s way. In C.

If a chain of failures cc:ars. the drst :ctneonent to mai.

general 2 for:ed shutdown is one that would not have been function should be bsted. The secuen:e of events.eciuc.

compieted in the absence of de :cndition for which orrechve ing the other components which tail should be des:nbed scucn was taicen.

under the Cause and Corteenve Action to Prevent Recur.

rence column.

DURATION. Self. explanatory. When 2 shutdown extends Components that do not et any exisung : ode shou,d be de.

.:eyond de end or. 2 report penod, count only the t:me to the ugnated.1%%%%1 The code 7777 7 should.:e used ter end ot the report penod and pick up the ensumg down ::=e events where s component designat:on is net appii scle.

n the foilowme reecrt =eneds. Re ort duration of outages yunded to the nearest teeth uf an hour to fac
litste summation.

CAUSE & CORRECTIVE ACTION TO PREVE.NT RECUR.

.he sum of the total outage hours plus the hours the gener2 RENC.e.

se me : iumn m a narranve fash on to am;itfy or tor was un Im.e should equal the gress hours in the reportmg expiam de :ircumstances of the shutdown or power recuenen.

E'" d-The :clumn shculd me!ude the tpectdc :suse for each snut.

down or sicudcant pnwer reduenen and the :mmediate anc REASON. Categonae bs,e ter demnanun m accordance contempiated long temt corre:nve action taken. if appropn.

witn e racie 2:peatmg on tne re: ort form. If:stegorv ri ams :otumn snould Mso be used tor a desen: tion of me ste.

must he ased. su pi) bnet eumments.

maior safety.re!sted actreenve mamtenance perfo med dunna NIETHOD OF SHUTTING DOWN THE REACTOR OR

  • 0"I*I'. ## EC*" *"*"0" ;"d"d*! sn : dent:6 :tien of

'hi '~'""#' E** ##"9 *dist:en ex csure s:ectC sily asses:.,

"# * "EC" 3' 2"Y ""I* * *23' #'

REDUCING POWER. Categortze ey numeer desiansuun rsctoactmty or smg:e ra 1% e that this differs from the Edisim E!ectn: Insuture atec wnh e ounge wtuch aemn for more m;n ;0 per.ent tEEll denrutions o1 " Forced Partt:1 Outage" anc "Sene.

di de 21!owse:e 2nnual values.

suled Pantal Outap." For these tenna. FE! uses a shange of For long textual repons contmue narrat;ve On se:2r;te "3:er

.0 stw s the breau ;mmt. For larpr power reactors. 30 31%

.nd tererense the shutcow n or power recu t:vn :vi.:

a

s t.u imall J. hang to *anant opiananon.

narrative.

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i IMMTiff NO.

50-315 I

IlNir SiltllDOWNS AND POWiin RiiDilCTIONS IJNil NAAII: D C.,_ Cook - Unit 1 l

l 83 DA Ili l

December,1982 CohtPl.lcIEn ny B.A. Svensson nl:POR I &lONIll

~Ilil.l:PilONE 616-465-5901 4

PAGE 2 of 2

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'b f, s' 5 Iii.cusce S e.,

j~3 Cause & Concoive Aui.ni su N...

Date g,

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liven 3y gO Pseveng Heciassonice y3 3 gh g Hcpogg ss ad O l'-

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190 ( Continued) service to repair coupling grease seal. Following coupling repair, the pump was placed in service and re-actor power increased to 70% and held there for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to observe. pump operation. Reactor power was increased to 100% on 821225, i

PUMPXX Reactor power reduced to 58% to re-191 821225 F

0 A

4 N. A.

CH move the west main feedpump from ser-1 vice to repair leak in bearing lube-oil system. Reactor power returned

]

to 100% on 821227.

1 i

I I

J J

4 I: h n ceil Reason:

kletioni:

lixintal G Insiinitions S. S61 cifulcil A I quipmer.: l.nline (1:xplain) 1 -klannal im Pac p. nation of D.ata 11 klainicnance os Tess 2-klannat Scsani.

linisy Sheels fm Iisensee i

l C Refueling

.1 Ansomatic & s.am.

1%cne l<epuse (I l'll) l'ile INilHI G-t D Hegiil.shny itessalainsi

-I Othee Ilimplaml 0161) l~ Opesaim l'saining & lircuse l'xamin.ilion it Ailmunstias ive 5

1:sintne I Sany Somce G Opciasional I nen llNplam)

[

l'8/ / / )

ll Ollies (l%pl. sin)

I

UNIT SHUTDOWNS AND POWER REDUCTIONS LNSTRUCTIONS Th:s report saould desenbe 111 plant shutdowns dunn; de m =::rdan:e wid de ta::e acceanng on de report form..

report penad. In additon.it should be the sour:e of explan.

If:stegory a must be used. suppiy bnef e:mments.

l 2non of sig:uncant dips :n aversge power levels. Each stam-ft:2nt redu:non ut power !evel (greater than 20'- reduc 5cn LICENSEE EVENT REPORT =. Reference de app!: 2:le m 2verage daily power leve! for de preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) aponscie oc:unence penazg to de outage or pown re m nen. :nur de S-n :our ;2ns (tunt year. sequen=

mould be noted, even dough ie umt =sy not have been snut down completely. For sucn reducuens in power leve!.

report numcer. oc:unence : de and report type) oc tne 5ve l

tne durst:on should be !!sted as zero,the medod of redu:non part designanon as desenbed in Item 17 or Instruenons tot should be 'isted as 4 (Other). 2nd de Cause 2nd Correenve Preparanon of Data Entry Sheets for L cenree Event Repon Acticn to Prevent Re:urrence column should excisin. The (LER) File tNUREG.0161). Th:s informanon may not se Cause 2nc Corre ::ve Action to Prevent Recurrence column

!= mediately evident for 211 such shutdowns of coune, smee should be used to provice any needed explanation to fully rurther :nvest:gation may be requ: red to ascertam whetner er desenbe the circumstances of the outage or power reduction.

not a re;ortable oc:urrence was involvec.) If tne outage or power reducnon wtil not result in a reportable oc:urrence.

NU5tBER. T'es :ciurna should ind!=te the sequent:21 num.

the posinve indi:st:en of its lack of ctreianon should be ber assigned to each shutdown or sigmAcant reduct on m power noted as not appli:able IN/A).

for tnat es!endar year. When a shutdown or s:gmScant power SYSTE31 CODE. The system in whi:n the outage or pcwer reduenon begins in one report pened sad ends :n 2notner.

reduenen ortg:nated should be acted.sy the two d;..2:t ecce or.

an entrv snouL.se made for botn re:on :enods to be sure

. icoit G. Instrucacns :. r Preparau n i Data catry sneets i

211 shutdowns or sisrud: ant power redu: Eons are reported.

cx Until a umt has 2:h'ieved its fir:t power generation no m:m-f r Ltcensee Event Report (LER) rue (SLREG.0161).

ber should be assigned to each entry.

Systems tnat do not fit any existmg : ode should :e destpa.

ted XX. The :oce ZZ should be used for dose events where DATE. This column should mdicate de date of the start a system is not appii: sole.

of each shutdown or signi!! cant power reduccon. Report as year. mcnth 2nd day. Aunst 14.1977 would be reported COh!PONENT CODE. Select de taost 2;ptcenate :omponent as 77CS14. When a shutdown or sigmScant power reduenen nom Exhibit ! - Instruenons for Pre =araucrt of Data Entn beg:ns in one report pened and ends in 2noder, an entry shou!d Sheets for Licensee Event Report (LER) File (NUREC.01615.

be made for bod report penods to be sure all shutdowns usmg de followtng entiena:

or sig:un:2nt power reductions are reported TYPE. Use "F or -S" to adicate either "For:ed" or " Sche.

duled." respe:avely, for each shutdown or signincant power B.

If not a :ompenent fat!ure, use de reisted cmpenent.

reduenon. Forced shutdowns in:!ade th2se required to be e.g.. wrong valve ocerated througn error: !ist valve as artisted by no later than the weekend fo!!owmg discovery comoonent.

cf an off normal ecndit:on. It ts recogmaed that some judg.

ment :s requ2 red in :stegonzmg shutdowns in t'ns way. In C.

If a enam of fattures occurs. the firs commonent to m:i.

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

completed in de acsen:e of the cendition for which corrective ing de other ::mponents wh::h fail. should be des:nbed acuan was taken.

under the Cause 2nd Corre:nve Acuan to Prevent Recur.

rence column.

DURATION. Self When a shutdown extends beyond the end or.-explanatory.

Comeonents that do not St any ex2stmg :cde should be de.

2 report penod. count only the uma to the signa'ted XXXXXX. T' e code 777777 should be used for end or.the recurt pened and =ic. uo the ensumg down ume events where 2 comeonent designat:en ts act applicacie.

m the tol:owmg repcrt penods. Report duracon of outages munded to tne nearest tenth of an hour to fac:litate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

ihe sum of the total vutage hours ;ius the hours the gener2 RENC.i... L.se the :clumn :n a narrative tastuon to am:itfy or tar was on line should equal the gross hours in the reportmg ex e m stances e

wn r pown recucucn.

E'"~"d

  • The :clumn snould in !ude the spec:Sc :suse for each snut.

down or sigm6c:nt power reducnon 2nd the immeciate anc REASON. Categortee by.etter deugnation :n accordance centemeisted long term correcuve acuen taken. if appropn.

with the rabie a::carmy on the report form. If:stegcry H ste. Th:s column snould also be used tot a desenetion of tne must be use3..sucpiv br:ei eumments.

maict safety.re!sted corre:nve mamtenance performed durma outage or pown reducen ;ndudmg an : dent:0:stien af 3tETHOD OF SHUTTING DOWN THE REACTOR OR j

REDUCING POWER. Categonze ey numoer destanst:en

  • '. #U""#I E**^ *# # 'F *^U * EC" O' *^Y 3d f* "

2',

ractosenvity or sinzle radist:en exposure s:ee:ttently assuet.

I% e that this differs trom the Edison E!ectne Insutut, ated with de out:ge wn:ch secounts for more thn :0 :er;ent

'l tEEll deAmnons of " Forced P2rus! Outage" and "Sene.

of de silowacie annual values.

duied P:rt:al Outaa." For mese tenm. eel uses 4 hange at For long textusi reports eentmue narrative on se:2rste racer l

.0 SIW as the creak romt. For larger puwer r:2etars. 30 St%

.nd referen e rise shutdown or power recu nun un a

.s fm amJll J ghange to WJriant oplanJtion, n3rrative.

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Docket No.: 50-315 Unit Name:

D. C. Cook Unit 1 Completed By:

C. E. Murphy Telephone:

(616) 465-5901 Date:

1/10/83 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - DECEMBER 1982 Highlights:

The Unit entered the reporting period operating at 59% power. The reduction in power was due to high vibration on the East Main Feedpump. The forced outage on the Feedpump occurred on Nov. 29 and after repairs were made to the.Feedpump/ Turbine Coupling, the Feedpump was returned to service at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on Dec. 3.

Unit power was increased to 62%, and at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on Dec. 3 a pressure test connection on the #2 Main. Steam lead to the High Pressure Main Turbine developed a leak. A power reduction to 30% was begun at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br /> with the reactor reaching 30% at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />. Repairs were completed to the test connection at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> on Dec. 3 and 100% power was achieved at 1423 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.414515e-4 months <br /> on Dec. 4.

At 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> on Dec. 22 power was reduced to 55% to remove the 1

~

West Main Feedpump to replace a grease seal on the Feedpump/ Turbine Coupling. The West Main Feedpump was returned to service at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on Dec. 24 and Reactor Power was increased to 70% at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br /> on Dec. 24. Due to system conditions, the Unit Power was held at 70% until 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> on Dec. 25 at which time the Unit reached 100%

power.

At 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> on Dec. 25, an oil leak developed on the West Main Feedpump Turbine and at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on Dec. 26 the Unit Power was reduced to 58%.

Following repairs to the West Main Feedpump the Unit was brought to 100% power at 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br /> on Dec. 27.

Reactor power was reduced to 95% two times during this period to test Turbine Control Valves. These are addressed in the Summary.

The gross electrical generation for the month was 747,420 MWH.

Summary:

12/10/82 95% power at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> for turbine valve testing. Returned to 100% power at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> on 12/11/82.

12/11/82 All C02 protection in the Auxiliary Building was out of service for a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period due to a loss of DC power.

to the C02 Isolation Valves.

12/17/82 95% power at 2322 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.83521e-4 months <br /> for turbine valve testing. Returned to 100% power at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 12/18/82.

12/21/82 The Control Room Pressurization Fan (HV-ACRF-1) was inoperable for a one hour period to tie-in Unit 2's S.I. Logic.

12/22/82 At 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br /> started reducing Unit power to make repairs to the "W" MFP Coupling. At 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />, Reactor Power at 55%.

"W" MFP removed from serivce.

1 Docket No.:' 50-315' Unit Name:

D. C. Cook Unit 1 Completed By:

C. E. Murphy Telephone:

(616) 465-5901 i

Date:

1/10/83 Page: 2 of 2 Summary: (cont'd) 12/24/82 At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> "W" MFP in service.

^

-At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />, increasing reactor power.

At 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br /> at 70% power.

12/25/82 At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, increasing reactor power.

At 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> at 100% power.

At 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br />, started power reduction - developed oil leak on the "W" MFP.'

12/26/82 At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> reactor power at 58%.

l At 0236 hours0.00273 days <br />0.0656 hours <br />3.902116e-4 weeks <br />8.9798e-5 months <br /> "W" MFP off for repairs.

12/27/82 At 0343 hours0.00397 days <br />0.0953 hours <br />5.671296e-4 weeks <br />1.305115e-4 months <br /> "W" MFP returned to service.

At 0407 hours0.00471 days <br />0.113 hours <br />6.729497e-4 weeks <br />1.548635e-4 months <br />, increasing reactor power.

)

At 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br /> at 100% power.

The #13 Steam Generator Stop Valve (MRV-230) was inoperable for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period while a leak on the dump valve was repaired.

I 12/31/82 95% power at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> for turbine valve testing.

Returned to 100% power at 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> on Jan. 1, 1983.

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DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No.1 DATE l-13-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE DECEMBER,1982 M-1 MRV-231, No. 3 steam generator stop valve dump valve was leaking by. Replaced the stem, plug, pin, cage and seat. Reassembled using new gaskets and had the valve tested.

C&I-1 Gland steam exhaust vent radiation monitor, R-33, failed low.

Power supply filter capacitor and voltage regulator were re-placed to restore operability to channel R-33.

0 C&I-2 Reactor coolant loop 3 AT indicator TI-431A was reading 7 to 100F above the other 3 loops. The loop 3 " cold leg" resistance temperature detector had failed. The spare cold leg RTD for this loop was connected in-circuit. Both hot and cold leg resistance-to-voltage converter modules were recali-brated to correct the loop 3 AT indication.

C&I-3 Upper containment area radiation monitor, VRS-1201, exhibited high readings up to 1R/ hour, while other redundant monitors were trending normally. A defective Geiger-Mueller radiation detector tube, V202, was replaced. Calibration of the system was completed and the channel was verified operable.

C&I-4 Steam jet air ejector flow meter, SFR-401, was reading about two times the actual flow rate. The transmitter, square-root extractor and recorder were recalibrated.

1

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