ML20112A984

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1985
ML20112A984
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/31/1985
From: Bruck D, Climer, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8503180546
Download: ML20112A984 (14)
v • d • e


Text

.. _ .

N.R.C. OPERATING DATA REPORT DOCKET NO. 50-316 DATE 2/4/85

COMPLETED BY CLIMER l TELEPHONE 616-465-5901 OPERATING STATUS

'1. Unit Name D. C. Cook Unit 2 =- -----

2. Reporting Period Jan. 85 Inotes i
3. Licensed Thermal Power (MWt) 3411 1  :! - ,
4. Name Plate Rating (Gross MWe) 1133 i 1
5. Design Electrical Rating (Net MWe) 1100 I ,1

) 6. Maximum Dependable Capacity (GROSS MWe) 1100 i

7. Maximum Dependable Capacity (Net MWe) 1060 -
8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons __________________ ____ _

__---------- - - - - - - - - - - - - - - - - = . -

9. Power Level To Which Restricted. If Any (Net MWe) _ _ _ _ _ - - __
10. Reasons For Restrictions. If Any:_____ ,'

a

_----------- = - - - - - - - - - - - - = - - - _

, This Mo. Yr. to Date Cumm. .

l 11. Hours in Reporting Period 744.0 744.0 62112.0 i

12. No. of Hrs. Reactor Wan Critical 453.0 .453.0 43533.0 i 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator on Line 434.5 434.5 42433.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Therm. Energy Gen. (MWH) 1361108 1361100 134439169
17. Gross Elect. Energy Gen. (MWH) 449860 449860 44235290 j 18. Net Elect. Energy Gen. (;WH) M 433635 433635 .42651369
19. Unit Service Factor 58.4 . 58.4 71.2-
20. Uni t Availabili ty Factor 50.4 58.4 71.2
21. Unit Capacity Factor (MDC Net) 55.0 55.0 67.6
22. Unit Capacity Factor (DER Net) 53.0 53.0 66.2
23. Unit Forced Outage Rate 36.2 36.2 13.0
24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):

, _ - - - _ - - - - - - - - - - - = - _ _ _ _ - - - . __

3 _ - _ _ .-- __ -- - - - - - _ _ - - _ _ _ _ _ - - - __

__- ==_-____-_

25. If Shut Down At End of Report Period, Estimated Date of Startup:

i

' ~ ~

~

26. Unite ~in T5sE~St$tus (Prior to CommerciA5~ Operation): ~~~

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY i COMMERCIAL OPERATION

? -

l 8503180546 850131 PDR

R ADOCK 05000316 PDR f+w

(

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO. 50-316 UNIT TWO ,

DATE 2/4/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH Jan. 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1

0 17 1049 2 0 18 1053 3 0 19 1052 4 0 20 1055 5 0 21 1055 6 0 7 22 1056 0 23 8 1054 G 24 9 1059 0 25 10 0 1057 26 414 11 0 27 349 12 0 28 1064 10 613 14 29 1082 G01 30 15 1002 1098 31 1091 16 1056 a

1 l  !

a DOCKE1NO. 50-316 .. .

UNIT Sill)IDOWNS AND POWEl( REDUCTIONS UNIT NAME D.C. Cook Unit 2 DATE 2-8-85 COMPLETED 11Y B.A. Svensson January, 1985 616/465-5901 REPORT MONTil TEl.EPilONE PAGE 1 of 3.

-, ,E E 3 Y 1.icensec [1 L Cause & Corsetlive Acison to No. Date ,o- 3g $ js$ livent g? 93 6- y3 y g Repius # vs O ' Psevent itecunscuce 6

156 841213' S&F 286.7 B 1 N.A. ZZ ZZZZZZ The Unit was removed from service on 841214 for a scheduled ice condenser surveillance outage. Following the performance of unplannea maintenance activities involving RCS RTD Loop Manifold Valves, the RCS was filled and vented, brought to rated tempera-ture and the reactor taken critical.

At this time a loose parts' event was indicated in Steam Generator No.

23. The reactor was shut down and the RCS cooled and drained to half loop to permit inspection of the Steam Generator. While shutting down, a loose parts' event was also de-tected in Steam Generator No. 22.

Inspections of Steam Generators Nos.

22 and 23 revealed parts from broken control rod guide tube split pins.

I 2 3 4 12: 1osced Reason: Meilusti: lixhibit G - Insiiuctions S: Schetfulcal A linguipmesis I;ailuie (1.xplain) 1 Manual for Psepasation of Data 11-Maintenance of Test 2 Manual Sciam. liniiy Sheets fo 1.icensee C Refueling 1 Automatic Si sam. liveni Repois ll 1:R) l'ile INilRIE D Regulatosy Restiiction -l-Olhes (lixplain) 0161)

ILOpenalos fraining & Iicense I:xamination ILAtiminisisalive 5 G-Ope ational tissos Ilixplain) lixinbit I - Same Somce 19/77) 1I Othes Ifixplain)

l

- 1 UNIT SHUTDOWNS AND POWER REDUCTIONS '

INSTRUCTIONS This report should desenbe a!! plant shutdowns dunng the :n accordance with the table appearmg on the report form.

report penod. In addition. it shou!d be the source of explan- If category 4 must be used. supply brief comments.

atton of signtScant dips m average power icve!s. Each sizni. ~

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT =. Reference the applicable m average daily power level for the preceding 24 hnurs) reportable occurrence pertaming to the outage or power should be noted, even thou h the umt may not have been reduction. Enter the Hrst four parts (event year. sequenttal shut down completely!. For'sud reducuans in power level. rep rt numcer, occurrence code and report type) of the rive the duration should be listed as zero, the method of reduction part designation as descnbed in Item 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 Acuan to Prevent Recurrence column immediately evident for all such shutdowns, or, course, since should be used to provide any needed explanation to fully rurther investigation may be required to ascertam whether or desenbe the :ircumstances of the outage or power reduction. not a reportable occurrence was involved.) If the outage or power reduction will nc: result m 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 sigmdcant reductionin power noted as not applicable (N/A).

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

an entry should be made for both report penods to be sure reduction onginated sh'ould be noted by the two digit code of all shutdowns or sigmscant power reductions are reported. ExWt G . Instmuons for Preparation or Data Entry heets 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 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 snutdown or signidcant power reduction. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770314 When a shutdown or ugnificant power reduction from Exhibit I . Instructions for Preparation of Data Entry begmsin one report pened and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161).

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

or ugmdcant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled." respectivelf , for each shutdown or signidcant power B. If not a component failure, use the related component:

reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated through errort list valve as imtiated 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 t!us 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. ine!ud.

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 existing code should be de.

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

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

The sum of the total uutage hours plus the hours the geners. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

The column should include the specific cause for each shut.

REASON. Categonze by letter deugnation in accordance down or siznificant power reduction and the immediate and with the table appearmg on the report form. If category H contemplated long term correcuve acuan taken, if appropn.

must be used.suppiy bnet comments. ate. This column should also be used for a desenption of the maior safety.related corrective maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot}

REDUCING POWER. Categonze by number designation the entical path aetmty and a report of any smale release et radioactmty or single radiation exposure spectrically asscet.

INote that this differs trom the Edison Electne Insuture sted with the outage which accounts for more than 10 percent iEEI) dedmtions of " Forced Parnal Outage" and " Sche. of the allowable annual values.

Juled Partial Outag." For these temt>. EE! uses a shange of For long textual recorts contmue narrative on separate raper 10 MW as the break ;mmt. For larger power reserors.30 MW and reference the shutdown or power redustaun foi ims is im small a Shange to wanant esplanation. narrative.

M7

"~ ~

DOCKET NO.

50-316 . .

IJNIT SulliDOWNS AND POWLu REDlu IlONS UNIT NAME D.C. Cook Unit 2 DATE 2-8-85 COMPT.ETED BY B.A. Svensson HLPORT MON'lli January, 1985 TEI.EPilONE 616/465-5901 PAGE 2 of 3

-- .y E 3 h* 1.icensee [ *,, t. Cause & Conective N. . Date F 75 $ }gg livens s? f3

n. Action to S j @E! $ jgg Hep.ni / 8'0 ' Prevens itecinsence 156 Following a thorough analysis of the (Conti nued) event, the Reactor Coolant System was again filled and vented and brought to rated pressure and temper-ature. The reactor was brought crit-ical and the Unit paralleled to the

. System on 840112. The power increase was terminated at 82% due to a in-dicated high quadrant power tilt problem. Total length of the outage was 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />.

157 850114 F 0 11 4 N.A. ZZ ZZZZZZ A reactor power reduction to < 50%

power was started due to the indi-cated quadrant power tilt. It was terminated at 52% when the quadrant power tilt was resolved. The cause of the quadrant power tilt was due to a nuclear instrument power range de-tector drift.

I 2 .) 4 1:: l'osced Heason: Heihnd: liminbis G - Insimciiivis S: Stheduleil A I?quipmesa 1 ailuie(1 xplain) 1-Manual for Pacpasalion of D.ala is Maintenance of Test 2 Manual Sciam. linsey Sheces foi 1.icensee C Refueling .1 Automatic Steam. livent Repose ll.l?RI l'ile iNilRI G.

D HeEnlaimy Hesisiciiim 4 Othes (limplain) 0161)

ILOpesaim I'saining a license 1:xamination 1: Aihninisseative 5 G.Og= saliinial 1:sini Ilixpl.sini lisliabit I Same Somce r1/17) 11 Othes (limplaini

~

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe 2!! plant shutcowns dudng de ;n accordance with the table appeanns on the report form.

report penod. In addition. tt should be the source of explan. If category a must be used. supply brief ecmments.

ation of sig:uAc:nt dips m 2verage power levels. Each ngm.

Scant reduenon m power level (greater man We reduction LICENSEE EVENT REPORT =. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportaole occurrence penammg to the outage or power should be noted, even though de urut may not have been reduction. Enter the erst four pans (event year. sequennal snut down ecmpletelyl . For such reduccons in power tevel, report numcer. occurrence c de and report type) of me rive the duration should be !!sted as zero, the method of reducnon part designation as desenbed in item 17 of Instruenons for Preparanon of Dats Entry Sheets for Lacersee Event Report should be listed as 4 (Other). :nd the Cause 2nd Correenve Acuen to P event Recurrence column should explain. The (LER) File (NUREC.0161). This information may not be Cause and Corre:nve Acucn to Prevent Recurrence column immed!ately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully turther investgation may be required to ascertam whetner ur desenbe the circumstances of the outage or power reduction. not a reportable occurrence was myolved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequentf21 num. the posinve indi:stion of tnis 1:ck of correlation should be her assigned to e:ch shutdown orsign Acant reduccon:n power noted as not applicable (N/A).

for that c:lendar year. When a shutdcwn or stgnificant power SYSTEM CODE. The system in which the outage or power reduction bestms m one report pened scd etds m another.

an entry shou!: be made for both recort penods to be sure reduction ngmated should be noted .oy the two dign ecde et.

all shutdowns or sia:ndcant power reduedons are reported. Exhibit G Instruenons for Preparation ot Data Entry sneets Until a urut h:s achieved its Erst power generstion, no num. for Licensee Enm Recort iLER) File (NLREG.0161).

bet should be assigned to each entry. Systems that do not Gt 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 appticable.

or eacn shutdown or sigmncant power reduccon. Report as year. month,2nd day. August 14.19'T7 would be reported COMPONENT CODE. Seie:t the most apprepnate camponent as 770814 When a shutdown or significant power reduenon from Exhibit ! Instruedens for Preparation of Data Entr>

begms m one repert penod and ends m anoder, an entr,* should Sheets for Licensee Event Report (LER) File (NCREG.0161).

be made for both report penods to be sure all shutdowns usmg the followmg critiona:

or sign 16:snt power reductions are reported.

A. If a ecmponent failed e the component directlyinvolved.

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

duled." resce:tively. for each snutcown or signi$ cant power B. If not a component failure. use de related ecmponent:

reduenon. Forced shutcowns include those required to be e.g. wrong valve operated through errort list valve as irutisted by no later than the weekend following discovery component.

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

ment is required in estegorizmg shutdowns in this way. In C. If a cham of fattures occurs, me Grst 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 correenve ing the other components which fail. should be desenbed scuon was taken.

under the Cause and Correenve Acuan to Prevent Recur.

rence column.

  • DURATION. Self. explanatory. When a shutdown extends beyond the end or 2 report penod. count only the time to de Components mat do not tit any existmg code should be de.

end or de report penoc and pick un the ensumg down nme signated XXXXXX. The code ZZZZZZ should be used for in te foiIowmg repert penods. Report durzuon of outages events where a component desagnation is not applicaole.

tuunded to me nearest tenth of an hour to factlitate summatiota.

The sum of the totd cutage hours plus the hours the genera. CAUSE & CORRECTIVE AC lCN TO PREVENT RECUR.

tor was on line shcuid equal the 3ross hours in ene reportmg RENCE. Use the column in a narrante fastuon to arnptify or penod. explam the circumstancas of the shutdown orpowerreducnon.

The column should include the specide cause for each shut.

REASON. Categonze by .,etter deugnanon m. accordance down or siamdcant power reduedon and the immediate anc with the taole appeanng un the report torm. If category H contemolated long term correcuw acnon taken. if approprt.

must he used.sueety bnet comments. ate. Trus column should also be used for a desenption of tne maior safety.related correcuve maintenance perictmed dunna METHOD OF SHUTTING DOWN THE REACTOR OR de outage or ;own reduedon mcfutne an idenude: tion of REDUCING POWER. Caegonze ov number ceugnacon the enneal path 2ennty and a report at sny smgle reiease at radiosennty or smale tsdianon exposure spectde:ily assect.

1% e that mis differs trom the Edison Electric Insuture 2ted with Me out:ge which accounts ror more than 10 :esent IEE!) denmt ens of " Forced Partial Outage" and "Sene. of me allowacle :nnual values.

uied P:rt:21 Out:ge." For tnese tenm. eel uses 4 hanse or For long textual reoorts ecmmue narrative en secar:te ;. aper

.t0 MW as the break ;mmt. For iarger power reactors. 30 MW .nd reteen e the snutdown or power reca.non foi tna

s t.u small a .nange to wanant espianation. narrative.

pp -

~' ' " '

50-316 .'.

DOCKET NO.

UNITSilUIIMlWNS ANilPOWER RElHRTIONS UNIT NAME D.C. Cook Unit 2 DATE 2-8-85 COMPT ETED gy B.A. Svensson REPORI MONTig January, 1985 TEl.EPilONE 616/465-5901 PAGE 3 of 3 e.

Causc & Cissse(live g $3 ) $ l.iccsascc h L Acis.uito N i. Ilate ,0-, E@ $ 2 s gg livcsis QT gU 3 8- y$ gE g Repent # e4 O Pseven1 Rccaesscurc 6

157 Reactor power increase was again commenced and leveled off at 96%,

(Continued) due to a Loop Delta-T power indica-tion problem.

850126 F 22.8 A 3 85-003-0 EF INSTRU A reactor trip occurred from 96%

158 '

power due to a failure of vital in-strument bus, CRID III inverter.

The inverter failure was due to a component short. The capacitor and diodes were replaced and the in-verter returned to service. During the outage the Loop 2 Delta-T prob-lem was corrected. The Unit was re-turned to service on 840127 at 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> and 100% reactor power was reached on 840128.

2 3 4 I .

Reasim: Meilueil: lixiobit G -Insinactiims 1-: 1:inced 1 Manpal fos Psepasatiini of Data S: Siliedulcil A I!ipapsucr.: 1 ailuse (l;xplain) 2-Manual Scsam. lintiy Sheets fin I.icensee la Maintenaisce oi Test C-Refuelisig 3-Ausnmaine Stsam. liven Repiua II.l?Rll'ile INLIRin D Regulaansy Restsicliam -l Oslies (lixplain) 0161)

I 1 Opciaans Isaining & Ikense I:xamination 12 Ailmeni:,asative 5

G Openasiimal 1:nns Ilimplam) lixlobal 1 Same Sonice PJ/1/) 11 Olhes ilimplaisil

. ; a. : . . . . . . . w. . . .

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS 4

This report should desence s!! plant shutdowns during de :n .ccordance with the tsole appearms on the report form.

repon penod. In addition. it should be the source of exp:an. If category 4 must be used. supply brief comments.

anca of sigmSc:nt dips :n aversge power levels. Each signi.

ricant reducuan iri power level (greater than 20"a reduction LICENSEE EVENT REPORT z. Reference the applicsble l

in average dady power level for tse preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportsole occurrence pertaming to the outage or power should be noted. sven though is unit may not have been reduction. Enter the Srst tour parts levent year, sequennal shut down completelyI . For such reductions in power level. repen numcer, occurrence ecds and report type) of the n,ve tne duration thould be listed as zero, the method of reducuan part designation as desenhed ut item i, at Instruenons for 4

should be listed as 4 (Other). 2nd the Cause and Correcuve Preparation of Data Entry Sheets for I.acensee Event Report

Action to Prevent Recurrence column should explsin. The (I.ER) File (NUREG.0161). This information may not be Cause 2nd Correenve Acton to Prevent Recurrence column immediately evident for all such shutdowns. or, course, since should be used to provide any needed expianation to fully rurther m.vestigaton may be required to ascertam whether ur describe the circumstances at tne outage or power reductiert. not a reportaole occurrence was involved.) If the outage or power reduction will not resu:t in a reportsbie occurrence.

NUMBER. This column should mdieste the sequent 21 num. the p sittve indicatien of this !2ck of corre!4tien should be ber assigned to each shutdown or sigmScant reduction in power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmricant power SYSTEM CODE. The system in which ths outage or power reduction begms m one report eened and ends m snother.

an entry should be made for both report oenods to be sure ggg g,, .

all shutdowns or siendcant power reductions are reported. Exasit G Instmnons for Paparation of Data Entry Shuts Until a unit has achieved its Erst power generation. no num. f r Ltcasee Ennt Repon @ER) Re MREWI).

ber should be assigned to each entry. Systems that do not Gt any existmg code should be designs-ted XX. The coce ZZ should be used for dose events where

{' DATE. This column should indicate the date of the start a system is not appiicable.

of each shutdown or sigmdcant power reduenon. Report as year. month 2nd day. August 14.1977 would be reported COMPONENT CODE. Select de most apptcpnate component as 770814 When a shutdown or sigmHcent power reduenort from Exhstt ! Instruccons for Preparanon of D:ta Entr>

begms m one report pened and ends m another, an entry should Sheets for Licensee Event Report (I.ER) Ftle (NUREG.016!).

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

, or ugmilcant power reductions are reported.

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

duled." respectively, for esen sautdown or signincant power 8. If not a ecmponent fadure, use the reisted component:

reducnon. Ferced shutdowns inciude mose required to be e.g., wrong valve operated through e rort list valve as imtisted by no later than the weekend following discovery comoonent.

of an off. normal cendition. It is reccgnized that some judg.

I ment ts required in categortz:ng shutdowns in this way. In C. If a chain of fadures occurs. the nrst component to msi.

j general, a forced shutdown is one that would not have been function should be listed. The sequence of events. inciud.

completed in the absence of the condition for which correenve ing the other components which fail. shou;d be desenbed action was taken.

under the Cause and Correcuve Acuon to Pavent Recur.

rence column.

DURATION. Se!f. explanatory. When a shutdown extends beyonc the end er a report penod. count only the time to the Components that do not St any existmg code should be de.

l signated XXXXXX. The code ZZZZZZ should be used for end or the report penod and pick uo the ensumg down uma In the fotlowmg repon menods. Report duranon of outages events where a component designation is not applicacie.

rounded :o the nearest tenth u(an hout to fac:litate summanon.

cat;SZ & CORRECTIVE ACTION TO PREVENT RICUR.

l the sum of the total outage hours plus the hours the geners.

I tor was on line should equal tne gross hours in the recortmg RENCE. Use :he column in a narrante fashion to ampiify or penod. explain the circumstances of 2e shutdown or power reducnon.

l The olumn should belude me speciSc cause for each shut.

REASON. CateIonae by tetter deugnation in accordance down or sigmdcant power reducnon and the tmmediate inc I

with the table appearmy on tne report form. If category H contemofsted long term correcuve acnon taken. if appropr:.

must he used. suppsy bnet comments. ate. This column should also be used for a descnotion of the maior safety.related correenve maintenance performed dunna METHOD OF SHUTTING DOwN THE REACTOR OR the outage or power reducten mcluding an tdent Sc:tton ot; REDUCING POWER. Categonze tw numner dessnanun tne entiesi path asuvtty sad a report at any smgie reiesse or rad;osenytty or smgje radiation exposure spee:desily asseet.

l%e that this dtifers imm the Edison E!estric Institute sted with the outsge wiuch accounts for more tnan 10 percent t EEI) dedmtions of "Furced Psru21 Outare" and "Sene. oi the 2ilc* sole annaal values.

Juled P:rita! Outm." For these terms. EE! uses a shange ut For long textual repcrts senttnue narrative an separate ; scer

?0 MW as the area ;wmt. For imer power ressters.30 MW atJ rererence the shutdown or power redu. nun foi tm.

s im small a ..unge to manant oplanatw. narranve.

p , -~

~'

l .

n Docket No.: 50-316 Unit Names D.C. Cook Unit 2 Completed By: D. A. Bruck Telephone: (616) 465-5901 Date: February 11, 1985 Page: 1 of 3 MONTHLY OPERATING ACTIVITIES - JANUARY 1985 HIGHLIGHTS:

The unit entered the reporting period with the Reactor Coolant System, RCS, in Mode 5 and in the process of heating up. The reactor was brought critical on 1-3-85. Approxi-mately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the reactor was critical a loose parts' event was indicated in Steam Generator No. 23. The reactor was shut down and the RCS cooled and drained to half loop to permit inspection of the Steam Generator. While shutting down, a loose parts' event was also detected in Steam Generator No. 22. Inspections.of Steam Generators Nos. 22 and 23 revealed parts from broken control rod guide tube split pins. Following a thorough analysis of the event, the Reactor Coolant System was again filled and vented and brought to rated pressure and temperature.

The reactor was brought critical on 1-12-85. With the reactor of 2% power a reactor trip occurred due to a low-low-level in No. 22 steam generator. The reactor was again taken critical and the Unit returned to service on 1-12-85.

During the subsequent power increase a quadrant power tilt problem occurred. The power increase was terminated at 82%

and a power reduction to < 50% power was started. The power decrease was terminated at 52% when the quadrant power tilt problem was resolved.

On 1-26-85 a reactor trip occurred due to loss of CRID III inverter. The problem was corrected and the Unit returned to service on 1-27-85. 100% reactor power was reached on 1-28-85.

The reporting period ended with the Unit at 100% RTP.

Total electrical generation for the month was 353,070 MWH.

SUMMARY

1-2-85 At 0125, the RCS entered Mode 4.

At 1055, the RCS entered Mode 3.

1-3-85 At 0628, the Reactor was critical.

At 1500, a controlled manual shutdown was begun due to the loose parts monitoring system showing impacts in

  1. 23 steam generator.

AT 2110, the RCS entered Mode 4.

a

Docket No.: 50-316

- Unit Name: D.C. Cook Unit 2 Completed By: D. A. Bruck Telephone: (616) 465-5901 Date: February 11, 1985 Page:- 2 of 3 1-4-85 At 1200, the RCS entered Mode 5.

1-6-85 At 0256, West Centrifugal Charging Pump was inoperable to inspect speed increaser. Returned to service at '

1110 on 1-10-85.

At 0715, the RCS drain to half loop was complete and the steam generators were inspected. Parts from broken split pins were found in steam generators #22 and 23.

1-10-85 At 1135, the RCS entered Mode 4. 1-11-85 At 0349, the RCS entered Mode 3.

At 1135, an ESF actuation occurred due to high-high level in #23 steam generator.

1-12-85 At 1411, the Reactor was critical.

At 1503, the Reactor tripped due to low-low-level in'

  1. 22 steam generator.

At 1928, the Reactor was critical.

At 2242, the Unit was paralleled to the System.

1-13-85 At 0738, the Reactor power increase was stopped at'49%

because of high quadrant power tilt.

At 0845, Reactor power increase began again until stopped at 1945 (82% RTP) because of high quadrant '

power tilt.

1-14-85 At 1438, a Reactor power decrease to 50% began to meet the quadrant power tilt Tech. Spec.

At 1632,.the quadrant power-tilt was within Tech. Spec.

limits. The problem was attributed to NIS Channel N-41 lower detector drift.

At 1633, the power decrease was stopped.at 52% and a power increase began.

1-15-85 At 1138, the Reactor power increase wasistopped at199%

due to an over power - AT alarm on Loop 2.

At 1430, a Reactor power decrease was started to clear the alarm. Reactor power reached at 96% RTP at 1450 and was held at this level pending resolution.of the difference between the AT power'and thermal power.

l l

Docket No.: 50-316

' Unit Nam 3: D.C. Cook Unit 2 Completed By: D. A. Bruck Telephone: (616) 465-5901 Date: February 11, 1985 Page: 3 of 3 1-16-85 At 0643, East Residual Heat Removal Pump was inoperable for lubrication. Returned to service to 0921 on 1-16-85.

At 0645, East Centrifugal Charging Pump was inoperable for lubrication. Returned to service at 1642 on 1-16-85.

1-17-85 At 0800, West Residual Heat Removal Pump was inoperable for lubrication. Returned to service at 0953 on 1-17-85.

1-23-85 At 1028, West Containment Spray Heat Exchanger and West Component Cooling Water Heat Exchanger were inoperable due to removal of Essential Service Water for valve repairs. Returned to service at 2019 on 1-24-85.

1-26-85 At 0925, the Reactor tripped due to loss of the CRID III inverter.

1-27-85 At 0241, the Reactor was critical.

At 0810, the Unit was paralleled to the System.

1-28-85 At 0952, the Reactor reached 100% RTP.

The Control Room Cable Vault Halon System remains inoperable as of 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on 4-14-83. The backup CO 2 System remains operable.

B DOCKET NO. 50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 2-8-85 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1985 M-1 Valve NRV-163, Pressurizer Spray from Loop No. 3 was rebuilt to eliminate leak-by. Inability to drain and isolate the system.

necessita'ted the use of freeze seals to affect the required re-pairs. Post-repair testing was performed to verify valve opera-bility.

M-2 Valve QRV-lll, letdown to the Regen Heat Exchanger was rebuilt to eliminate a body-to-bonnet leak. The valve was r@ tasted '

after repair to verify operability.

M-3 The inboard bearing on the "W" Centrifugal Charging Pump Motor failed in service. The failed motor was replaced by a spare and the pump was test run to verify operability.

M-4 The 612' elevation inner airlock door seal test air line was observed.to be leaking. _ Inspection revealed a broken 1/8 inch pipe nipple. The broken nipple was ?.eplaced. Airlock door seal testing was performed with satisfactory results.

M-5 Valve WM0-738 ESW from 2W CCW HX was found to have a badly worn seat. The defective valve was removed and a replacement valve was installed. Retesting verified proper operation of the re-placement valve.

M-6 Cell No. 55 in 2AB Battery failed to meet specified acceptance criteria during the performance of weekly surveillance. The cell was jumpered out and the battery was placed on equalize charge.

C&I-l Steam generator level transmitter BLP-122 was failed low inter-mittently. The transmitter was replaced and calibrated and the loop surveillance test procedure was performed.

C&I-2 The loop 2 Tavg was reading higher than the other loops. AT was reading-lower than the other loops. The cold-leg RTD was re-placed and its R/E was recalibrated. All four loops then read in close agreement.

C&I-3 Train A of the Post Accident Containment Hydrogen Monitor would not calibrate, and there was no sample flow. The regulator and

sample pressure gauge were replaced. The amplifier circuit board l of the analyzer was also replaced.

.I l ,A L -' ._ _ _ . _ . . _

F-4 DOCKET NO. 50 - 316 ~

UNIT NAME D. C. Cook - Unit No. 2 DATE 2-8-85 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAIhTENANCE JANUARY, 1985 C&I-4' An urgent failure was received on rod control. It could be cleared but came in again when Operations attempted to move the rods. Oscillator card A101 had failed and was replaced. Rod control then worked properly.

C&I-5 VCR-20 would not open after testing. The Asco Solenoid valve XS0-20 was repaired. The limit switches required adjustment and the valve was retested successfully.

p e

O

~~;m__ INDIANA & MICHIGAN ELECIBIC_COMPANL Donald C. Cook Nuclear Plant P 0. Box 458. Brusgman, Mctugan 49106 1

l February 8, 1985 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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of January, 1985 is submitted.

Sincerely, LA) / h W. G. Smith,Jr.q Plant Manager WGS:ab Attachments cc: J. E. Dolan M. P. Alexich R. W. Jurgensen h3C Region III B. L. Jorgensen R. O. Bruggee (NSAC)

R. C. Callen S. J . Hierzwa R. F. Kroeger B.11. Bennett P. D. Rennix J. H. Hennigan Z. Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department I

- s\

Retrieved from "https://kanterella.com/w/index.php?title=ML20112A984&oldid=2919568"