Text

Monthly Operating Rept for Aug 1984
	ML20093H193
Person / Time
Site:	Cook
Issue date:	08/31/1984
From:	Gillett W, Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8410160197
	Download: ML20093H193 (12)
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DCCI*I NO.

50-315

~

DATI 9-5-84 COS:?!~ IC 'Y W 'P Cillet-TI*.I?-iCNE K 1 A-a 6 5-5 9 0

_C???X"'*NG 5'AT*.:S

1. Urd: N:==:

Donald C.

Cook 1

Norn R.-,or".,-.* d.o e.

August 1984

3. U---

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3250

4. N== !:i: R.:i.;(Cro:s.'.!W:):

1152 S. Desi;:I::=i=! ?..:in;(Ne SIWE):

1n1n

6. If-d n::= Dey::.d:hte Gy::i:f (Cress 51We):

1056

7. SI:xi=== Dep::d:h!: t -- =:7 (N 5!We):

1020 S If Ch:=;;: 0:=:in Q :ii:y R::i=;:(1:==s Nu=he 3 T.'.:: ;.h -) SI::: I.=:R: par:. Give R:==ns:.

7

9. Power Leve! To Whi:2 R==i=:d. If Any (N:: 3:W:):

8

10. R esor.s.ror ?.::=i:d:::.If A=y:

T'.d.s 5 tor.th Y:..to. Cat:

Cu==lcive

11. Hour:!= R: c: ia; ?::i:d 744 moan 84,743

12. Nc=he of Hots R==:r W:: Cri: =1 492.3 s1as_n be,/b4.u

13. Re:== R=r.e:ve s':::down H::::

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14. E=== cen:=::: ca.L:=

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15. U..!: R=.::ve Sh=:down Ec:==

0 0

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16. Crc s Th==:! E==:;r Cen:=::d (5:WH)

I'349'6b/

15,524,904 181,218,617

17. Cross Ee==:=iI:=;y Cen:=::d G.tWH) 426.47_0_,

5,070,850 ga oo7_3gn

13. N : E :=i=! Z:=;y Cc =::d C.!WE) 409,192 4,882,754 qg ; 7,; 4 ; 13o

19. Uni: Seni=.::=:r 62.7 86.9 74.3

20. Uci: Av:iI:hi!!:y.::::::

62.7 86.9 74.3

21. Uni: Q:::i:.' :=:r (Usi=; >!rC Net) 53.9 81 B

22. Uni: Q::ci:y.::==r (Usin; OIR Ne:I 53.4 _

67.4 81.0 64.6

23. Uni:. or::d Cu::;e R:::

5.2 7.6 7.8 i

24. Sh::dowr.s Scheduled Cver Nu: 5 Sion:h:(Ty;.C=.: d 0 =0:n of E::i1:

Ten Year ISI Surveillance and Refueling Outage Schedule to Start on Marcli 1,1985.

Estimated duratic1 Four Months.

l

25. If Sh : Down At End CT R::::: ?=ied. I.::i==:ed "hre ei 5:: ::::

l

. 5. Units la Tc:: S::: s i?nor :o C:=:::=i:! 0;;: ::fon2:

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8410160197 840831 PDR ADOCK 05000315 u*I

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AVERAGE DAZLY UN1T POWER LEVEL 00CKET NO. 50'-315 UNIT

-1 DATE 9/4/84-COMPLETED BY A. Might

, TELEPHONE (616) 465-5901 MONTH Augusti 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 17 923 2

18 978 3

19 1017 4

20

~1021 5

21 1014 6

22 1011 7

23 877 8

24 548 9

25 546 10 25 659 11 239 27 988 12 1007 28 1007

-13 1021 29 991 14 604 30 985 15 53 31 865 t

16 677 INSTRUCTICNS

.t On this fonnat 1.ist the averace daily unit pcwer-level in MWe-Net for each y n the recortina month. Ccmnute tn *Sa

-n.,..,,....u_3.__......

s - - - -

C DOCKET NO. 50-315 UNITSilUTl) OWNS AND POWER HEDllCTIONS UNIT N AME D.C. Cook - Unit 1 DATE 9-13-84 COMPLETED HY B.A. Svensson REPORT MON ill AUGUST, 1984 TELLPilONE 616/465-5901 PAGE 1 of 3 e,

.$E 3

Y Eicensee E '*.,

L Cause & Canieceive No.

Dale B,

7: g s

,2 s &

livent gy e-3 Acis.m in jE 3 ;g g Rep.nl #

mO E'

Preven Recmsence t-m u

O 225 840727 S

250.6 B

1 N.A.

ZZ ZZZZZZ The Unit was removed from service to Cont'd, perform required ice condenser sur-veillance and to repair leaking pres-surizer safety valves. The pres-i surizer safety valves were replaced with rebuilt valves. The Unit was returned to service on 840811 and reached 100% power on 840812. Total length of the outage was 347.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

226 840814 F

27.2 A

3 84-018-00 EF INSTRU A reactor trip with Train "A" safety injection occurred from 100% power due to a failure of vital A.C. In-strument Bus, CRID IV Inverter. The inverter failure was due to water vapor laden air being blown into the inverter cabinet by a temporary ven-tilation blower. The water source was due to a leak. The inverter was replaced with a spare. The Unit was 1

2 3

4 1: Fm ce.1 Reauna Metin>il:

Exinbii G - Insiinctions S: Scliciluleil A.Equipmes.: Failme(Explain)

1. Manual int Pacpaiation of I)ata ll4taintenance oi Test

.! Manual Sciam.

Entey Sliccis fo: 1.icensee C-Refueling 3 Automatic Stram.

livens Repine ll.l!R) File INtlRIL D Regulasoiy Resisiction 4 Oilies (lixplain) 0161)

ILOpciaans l~s.sining & license lixamination F-Atiminislealive 5

i G Opesational tissos IExplaml ITinbit I Same Souice 19/77) 11 Ollier (lixpl.ain)

UNIT SHUTDOWNS AND POWER PEDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form, report penod. In addition,it should be the source of explan.

If category 4 must be used supply brief comments.

atton of signincant dips in average power levels. Each signi.

ficant reducuon in power level (greater than 20% reduction LICENSEE EVENT REPORT =. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) rep rtable occurrence pertammg to the outage or power should be noted. even though the unit may not have been reduction. Enter the Srst four parts (event year, sequent:al l

shut down completely. For such reductions in power level, rep rt number. occurrence code and report type) of the tive the duration should be listed as aero, 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 Preparauon of Data 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 Correenve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smee should be used to provide any needed explanation to fully turther mvestiganon may be required to ascertain whether or describe the circumstances of tne outage or power reduction.

n t a rep rtable occurrence was involved.) If the outage or power reduction will not result in a eportable occurrence.

NU5tBER. This column should indicate the sequential num.

the positive indication of this lack of correlation should be ber assigned to each shutdown or sigm5 cant reductionin power noted as not applicable (N/A).

for that enlendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period 2 td ends m another.

reducticn onginated sh'ould be noted by the tw'o digit eode of an entry should be made for both report periods to be sure all shutdowns or sigmHcant power redu:nons are reported.

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

of each shutdown or signincant power reduction. Report as year. month. and day. August i.t.1977 would be reported COMPONENT CODE. Select the most apptcpriate component as 770514 When a shutdown or s:gnificant power reducnon from Exhibit ! Instruenons for Preparation of Data Ent:3 begms in one report pened and ends in another. an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

be made for both report penods to be sure all shutdowns using the following critiena:

or sigmilcant power reducuans are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.

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

If *.ot a component failure, use the related component:

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 condition. It is recognised that some judg.

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

If a chain of failures occurs. the first cornponent 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 correenve 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 a shutdown extends Components that do not fit any existmg code should be de.

beyond the end or a report penod. count only the time to the signated XXXXXX. The code 777777 should be used for end or the report period and pick up the ensuing down time in the followmg report penods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTIO.4 TO PREVENT RECUR.

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

RENCE. Use the column in a narrative fasluon to ampiify or tot was on line should equal the gross hours m the reportmg explain the circumstances of the shutdown orpower reduenon.

penod The column should include the specific cause for each shut.

down or significant power reducuon and the immediate and REASON. Categonze by letter deugnation in accordance with the table appearmg on the report form. If category H contemolated lona term correente action taken. if appropn.

ste. This column'should also be used for a descriptica of the must be used. suppiy brief comments.

ma or safety.reisted corrective mamtenance performed dunna METHOD OF SHUTTING DOWN THE ~ REACTOR OR the outage or power reduction including an identification ot}

REDUCING POWER. Categonze t'y number designation the entreal path acavity and a report of any smgle release et radioactivity or single radiation exposure speettiestly associ.

INote that this differs from the Edisim Electne institute ated with the outage which accounts for more than 10 percent (EEI) detinitions of " Forced Partial Outage" and " Sche, of the allowable annual values.

duled Partial Outage / For these c. nn3. eel uses a shange or For long textual reports continue narrative on separate paper 30 MW as the break pomt. For larger power reseturs. 30 MW and reference the shutdown or power redustion do th:2 is em > mall a change to warrant explanation.

narrative.

(9'77

~~

~

4 V w

DOCKET NO.

50-315 UNIT SiluTDOWNS AND POWER REDUCllONS D.C. Cook - Unit 1, UNIT NAME DATrj 9-13-84 AUGUST, 1984 COMPLETEp isY B.A. Svensson REPORT MONTil TELEPilONE 616/465-5901 PAGE 2 of 3 e.

jE 3

Y 1 icensee

,E's,

Cause & Conective i

Acti.ri to No.

Date g,

yg

.c y y livent gy gU j$

3 ;y, g Repius #

mV Prevens Recturence I--

o e

u

,o 226 returned to service on 840815 and re-ContN actor power reached 100% on 840816.

227 840817 F

0 H

4 N.A.

1111 TURBIN Reactor power was reduced from 100%

l to 80% for approximately 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months to reduce the loading of the east main feed pump turbine due to a high vi-bration problem on the turbine in-board bearing.

228 840823 F&S 0

B 4

N.A.

IIH HTEXCII Reactor power was reduced from 100%

to 58 to first remove the west main TURBIN feed pump turbine to repair conden-ser tube leak. One tube was plugged.

The west MFPT was then placed in ser-vice and the east MFPT removed from service to repair the turbine inboard bearing oil leak and the cause for the.high vibration still being ex-perienced on this bearing. The east MFPT was returned to service and 1

2 3

4 F: Finceal Reason:

Method:

Exhibii G - Insinuctions 1

S: Sdiciluleil A-Equipmen Failme(1;xplain) 1 Manual for Pseparation of Data li Maintenance or Test 2 Manual Scram.

Entey Sheets fia Iicensee C-Refueling 3 Automatic Str.un.

Evens Repoit (1 l:R) File (NURI G-D Regulasiuy Resleiction l-Oihes (Explain) 0161)

I?Opesato l'saining & Ikense !!xamination F-Asiminisirative 5

G Opesational Enos (lixplain)

'tisinbu ! - Same Somce (9/77) ll Ot her (lixplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report period. In addition,it should be the source of explan-If category 4 must be used. supply brief comments.

ation of significant dips in average power levels. Each sieni-ficant reduction in power level (greater than 20"e reduction LICENSEE EVENT REPORT. Reference the applicable

~

in average daily power level-for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportaole occurrence penaining to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequent:a1 l

shut down completely. For such reductions in power level, rep rt number, occurrence code and report type) of the Sve the duration should be listed as zero. the method of reducuan part designation as desenbed in tem 17 of Instrucuons for should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data 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 Correcuve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since 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 reducuen.

not a reportable occurrence was involved.) If the outage or pcwer 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 or sigmilcant reductionin 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 m another, SYSTEM CODE. The system in which the outage or power an entry should be made for both report penods to be sure reduction ongmated sh'ould be noted by the tw"o digit code of all shutdowns or siamilcant power reducuans are reported.

Exhibit G. Instructions for Preparation of Data Entry sheets Until a unit has ach'ieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG4161).

ber should be assigned to each entry.

Systems that do not fit any existing code should be 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 signidcant power reducuon. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the mest appropriate component as 770S14. When a shutdown or sigmficant power reduction from Exhibn I instructions for Preparation of Data Entry begmsin one report penod and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NCREG4161).

be made for both report periods to be sure all shutdowns using the following critieria:

or sigmiice.nt 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:

reducuen. 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 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 first 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 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 fit any exntmg code should be de.

end or the report penod and pick up the ensumg down time signated XXXXXX. The code 777777 should be used for in the following report penods. Report duranon of outages events where a component designanon is not appticable.

rounded to the nearest tenth of an hour to facilitate summation.

The sum of trie total outage hours plus the hours the genera.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

tor was on line should equal the gross hours m the reportmg RENCE. Use the column in a narrative fashion to ampitfy or pen d.

explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut-REASON. Categonze by letter deugnation in accordance down or sigmficant power reduction and the immediate and with the table appearmg on the report form. If categeev H contemplated long term corrective acnon taken if appropri.

must be used, suppiy brief comments.

are. This column should also be used for a desenption of the ufety.related corrective maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Categonee by number designauon the entteal path acuvity and a report of any smgle release or, radioactivity or smgle radiation exposure specifically associ.

INote that this differs from the Edison Electrie insutute ated with the outage which accounts for more than 10 percent t EEI) definitions of " Forced Parnal Outage" and " Sche.

of the allowable annual values.

duled Partial Outage." For these terms. eel uses a shange of For long textual reports continue narrative on separate paper 30 MW as the break pomt. For larger power reactors.30 MW and reference the shutdown or power redu tion for trm

s im small a change to wartant esplanation.

narrative.

W77

~ ' -

m,_

50-315 DOCKETNO.

UNil SHUIIH)WNS AND POWE't REDUCTIONS UNIT NAME D.C. Cook - Unit 1..

I) ATE 9-13-84 COMPl.ETED itY B.A. Svensson RFPORT MON I'll AUGUST, 1984 TEl.EPilONE 616/465-5901 N

PAGE 3 of 3 a.

b <t E

'E Y Eb caust & reniective 1.icensee E-,

No.

Dale h

j$

k

)!$

h Action so I!vens g'

Prevens Recmrence yE y

j;jjg Repose u un o t-6

~

228 reactor power increased to 99% on Cont'd 840826.

229 840831 F

0 S

4 N.A.

Illi TURBIN Reactor power was reduced to 57% to remove the east main feed pump tur-bine from service to make alignment checks and replace the turbine in-board bearing with a new design (elliptical) bearing. The east MFFT was returned to service on 840902 and reactor power _ returned to 100% on 840904. The oil leak has been re-paired and no vibration excursions have been experienced since the bearinj; replacement.

I i

1 2

3 4

1:: Foiced Re.ison:

Method:

lix'nbis G Insinicsions S: Sc hedu'ed A Equipmesa I;ailme(1-xplain) 1 -Mm ial los Pseparation of Data i

li Maintenance of Test 2 Manual Scram.

lini y Shecis fo 1.icensee r Refueling 3 Aniomatic Scram.

livent Repius (1.0Rn file (NilRIE D Regulatoiy Resisiciion 1-Othes (lixplain) 0161)

ILOpesaio l' raining & l.icense lixamination F Aiiministsative 5

G Opesational liasos (lixplini INiobit 1 - Same Somee PJ/77) ll Other (lisplain)

.a UNIT SHUTDOWNS AND POWER REDUCTIONS l

INSTRUCTIONS j

This report should desenbe all plant shutdowns during the in accordance with the table appearing on the report form.

report penod. In addition, tt should be the source of explan.

If category 4 must be used. supply brief comments.

l stion of sigmficant dips in avers;e power levels. Each signi.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT =. Reference the applicsole in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pertaining to the outage or power should be noted, even thoua reduction. Enter the first four parts (event year. sequennal

. shut down completely. For'h the unit may not have been l

such reductions in power level, report number, occurrence code and report type) of the tive the duration should be listed as zero, the method of reduction 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 Licensee Event Report Action to Prevent Recurrence cc'umn Aould explain. The (LER) File (NUREG-0161). This information may not be Cause 2nd Currecuve Action to Prevent Recunence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully turther 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 outage or power reduction will not result in a reportable occurrence.

NU31BER. This column should indicate the sequential num.

the positive indication of this lack of correlation should be ber assigned to each shutdown or sigmneant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmficant power SYSTE31 CODE. The system in which the outage or power reduction begms in one report penod and ends m another.

reduction onginated sh'ould be noted oy the tw'o digit code of an entry should be made for both report penods to be sure all shutdowns or sigmScant power reducnons are reported.

Exhibit G. Instructions for Preparation of Data Entry Sheets Unt:1 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 existing code should be designs.

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 reducnon. Report as year. month, and day. August 14.1977 woujd be reported COSIPONENT CODE. Select the most appropriate component as 770814. When 2 shutdown or significant power reducuan from Exhibit !. Instructions for Preparanon of Data Ent:3 begmsin one report pened 2nd ends :n another. an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

be made for both report penods to be sure 2!! shutdowns using the following entiena:

or s:g:uscant 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 re!ated component:

reducuon. Forced shutdowns include those required to be e.g.

wrong valve operated through erron list valve as initiated by no later than the weekend following discovery component.

of an cif. normal condition. It is recognised that some judg.

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

If a chain of fattures occurs, the first component to mai.

genera. a forced shutdown is one that would not have been function should be listed. The sequence of e5ents. iaciud.

core.pleted in the absence of the condition for which corrective ing the other components which fait should be desenbed action was taken.

under the Cause and Corrective 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 fit any existmg code should be de.

signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensuing down time m the following report penods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to fac:litate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

tor was on line should equal the gross hours m the reportmg RENCE. Use the column in a narrative fashion to ampiify or penod.

explain the circumstances of the shutdown orpower reduction.

The column should include the soecine cause for each shut.

wn r gnu am p wu uen n and th immdate ad REASON. Categonze by Ietter designation in accordance with the table appearmg on the report form. If category H contemplated long term correenve action taken. if appropn.

must be used, supply brief eumments.

ate. This column should also be used for a desertption of the ufety.related corrective maintenance performed durma AtETHOD OF SHUTTING DOWN THE REACTOR OR the outage or power recuction including an.denufication ot}

REDUCING POWER. Categonze by number designation the ent: cal path activity and a report of any smgle release et radioactivity or single radiation exposure speetfiesily associ.

[ Note that this differs trom the Edison E!ectrie Institute ated with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Pamal Outare" and " Sche.

of the allowable annual values.

duled Partial Outage." For these terms. eel uses a shange or For long textual reports eontinue narrative on separate paper i

[

30 SIW as the break pomt. For larger power resetors.30 5tW and reference the shutdown or power redu tion for tini is im sm.iil a sh.mge to warrant explanation.

narrative.

op7"

~~

'~

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9--.-m

.E

1-Dcckst No. : 315 Unit Namn D.C. Cook Unit 1 4-Completed By:

'G. J.JPeak

. Telephone:

.(616)L465-5901-Date:.09/07/84 Page:

1 of 2 MONTHLY OPERATING' ACTIVITIES - AUGUST, 1984

~

HIGHLIGHTS:

-The. unit. entered the reporting period'in Mode 5 with the Reactor Coolant System at the half: loop-elevation due'to~an ice condenser surveillance outage.

The surveillance.

requirements were completed and the Unit was returned to service and loaded to 100% power.

The Crid IV inverter failed on 8-14-84 causing a reactor trip and Train A-safety injection.. The inverter was replaced and the unit was subsequently' returned to 100% power-where it was operat-ing when the reporting period ended. - Major power reductions-occurred to remove the West Main Feed Pump from service for a condenser tube leak-check and to remove the East Main Feed Pump from service due to high vibration.

Total electrical generation for the month was 426,470 MWH.

a

SUMMARY

i 8-06-84 The Reactor Coolant System was filled and vented at 2035 hours0.0236 days 0.565 hours 0.00336 weeks 7.743175e-4 months following an ice condenser surveillance outage.

8-07-84 Mode 4 was entered at 1818 hours0.021 days 0.505 hours 0.00301 weeks 6.91749e-4 months .

8-08-84 Mode 3 was entered at 0623 hours0.00721 days 0.173 hours 0.00103 weeks 2.370515e-4 months .

8-10-84 The reactor was critical at 1450 hours0.0168 days 0.403 hours 0.0024 weeks 5.51725e-4 months .

1 8-11-84 The main turbine was rolled at 0856' hours.

The-main -

generator was paralleled at 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months .

8-12-84 Power reached 100% at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

8-14-84 The unit tripped and a Train A safety injection occurred at 1529 hours0.0177 days 0.425 hours 0.00253 weeks 5.817845e-4 months due to the failure of crid'IV.

1 i

8-15-84 Crid IV was declared operable at 0944 hours0.0109 days 0.262 hours 0.00156 weeks 3.59192e-4 months and the reactor was made critical at 1225 hours0.0142 days 0.34 hours 0.00203 weeks 4.661125e-4 months .

Mode 1 was.

j entered at 1445 hours0.0167 days 0.401 hours 0.00239 weeks 5.498225e-4 months .

The main. turbine was rolled at 1734 hours0.0201 days 0.482 hours 0.00287 weeks 6.59787e-4 months .

The main generator was paralleled-at-1841 hours, l

8-16-84 Power reached 100% at 2133 hours0.0247 days 0.593 hours 0.00353 weeks 8.116065e-4 months .

)-

8-17-84 Power was reduced to 80% at 1350 hours0.0156 days 0.375 hours 0.00223 weeks 5.13675e-4 months due to high vibration on'the East Main Feed Pump.

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~ Unit-Namn:

D.C.' Cook' Unit 1 Completed By:

G. J._ Peak Telephone:' ^ (616) 465-5901-Date:

09/07/84 I

Page:

2 of 2 8-18-84 Power was returned to 100% at 0825. hours.

4-

.8-23-84

- Power was reduced to'58%'at 1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months .to remove'the West Main Feed-Pump;from service for a condenser tube

- leak check.

1 8-24-84 The West' Main Feed Pump-was returned to service.at 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and the East Main: Feed Pump-was removed from

- service at 0529 hours0.00612 days 0.147 hours 8.746693e-4 weeks 2.012845e-4 months to repair a bearing oil seal' leak.

'8-26-84 The East Main Feed Pump was returnedLto service at 1224 hours0.0142 days 0.34 hours 0.00202 weeks 4.65732e-4 months and a power increase began at 1410' hours.

Power-reached,99% at-2249 hours when 'the East 14ain Feed Pump indicated-high vibration.

Therefore, power was. reduced f

to 88% at 2257 hours0.0261 days 0.627 hours 0.00373 weeks 8.587885e-4 months ..

4 8-27-84 The unit was loaded to 100% at 0456 hours0.00528 days 0.127 hours 7.539683e-4 weeks 1.73508e-4 months ._ Power was reduced to 92% at 1657 hours0.0192 days 0.46 hours 0.00274 weeks 6.304885e-4 months due~to high_ vibration on the East Main Feed Pump.

The unit was returned to 100%

power at 2146 hours0.0248 days 0.596 hours 0.00355 weeks 8.16553e-4 months .

8-29 Power was reduced to 92% at 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months due to high vibration on the East. Main Feed Pump.

Power was re-turned to 100% at 1027 hours0.0119 days 0.285 hours 0.0017 weeks 3.907735e-4 months .

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8-30-84 Power was reduced to 97% at 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months due to high vibration on the East Main Feed Pump.

f 8-31-84 Power was further reduced'to 57%~at 2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months in order j

to remove the East Main Feed Pump from service.

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 backup Co System for the Control m

l Room Cable Vault remains operable.

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UNIT NAME D. C. CookL--Unit No.fl DATEJ 9-13-84

~'

COMPLETED BY

'B.-A. Svensson TELEPHONE:

(616) 465-5901 PAGE~

- 1. of 1-

'MAIOR' SAFETY-RELATED MAINTENANCE

. AUGUST. 1984 M-1 Checked operation of 1 "E" ESW Pp Breaker. 'Found defective-anti-pump relay. Replaced relay and performed electrical test to verify proper operation.

M-2' Repaired Pressurizer PORV's, NRV-151, NRV-152 and NRV-153,

.as required to eliminate seat. leakage. Valves performed sat-

~

isfactorily when: retested.

M-3 Replaced plunger,' throat bushing, and repacked reciprocal-charging pump. Ran' pump to verify packingLleakage within acceptable limits.

M-4 Investigated reason for breaker tripping when attempting to operate emergency boration valve, QMO-410. Found open winding in limit torque motor and replaced motor. Retest was performed and valve functioned properly.

M-5 Repaired ice condenser intermediate deck doors to pass lif ting test. Door ll-C was replaced. Surveillance test was performed after repairs to verify operability.

C&I-1 The critical control room power inverter failed. Capacitor C2 and fuse FU2 were replaced..The diodes and SCR's were tested and were OK.

The inverter was restarted and returned to service.

C&I-2 Steam dump URV-120 did.not open in cooldown mode. The solenoid valve's coil was open. The coil was replaced. The solenoid valve then worked properly.

C&I-3 Containment isolation valve ECR-32 would not close and ECR-31 would not indicate it was closed. The solenoid valves for both valves were leaking by and were rebuilt. The valves then worked properly and ECR-31 and ECR-32 were tested for proper closing times.

C&I-4 QRV-51, auxiliary spray to the pressurizer had failed closed.

The coil of solenoid valve XS0-51 was measured and found open.

The coil was replaced and the valve was verified to open and close properly.

C&I-5 Loop 4, Tavg indication failed low. Dynamic compensator module TY-442A was found to be defective and was replaced and calibrated.

The AT/Tavg system was verified to be operable.

huyz s.,-

c t --

/Uy,r.. IMOMMA & MICMGAN ELECTRIC C.DMPAMX Donald C. Cook Nuclear Plant P.O. Bau 458. Bruigman, Mchigan 49106 September. 13,-1984 -

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 August, 1984 is submitted.

Sincerely, iA U W. G. Smith, Jr.

Plant Manager WCS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen i

NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa i

R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan Z.

Cordero R. F. Hering J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department d

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ML20093H193

Text

SUMMARY

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