ML20106J415

Monthly Operating Rept for Dec 1984

ML20106J415
Person / Time
Site:	Cook
Issue date:	12/31/1984
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8502150623
Download: ML20106J415 (10)

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OPERATING DATA REPORT

Q DOCKET NO.

50-316

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DATE 1/4/85

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COMPLETED BY CLIMER

-gi TELEPHONE 616-465-5901 bIOPERATING STATUS JM)',

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1. Unit Name D.

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Cook Unit 2

.2 Reporting Period

.Dec.1984 l notes I

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'3. -Licensed Thermal Power (MWt) 3411 1

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4. Name Plate Rating (Gross MWe) 1133 1 J

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" 5. Design Electrical Rating (Net MWe) 1100 I

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6. Maximum Dependable Capacity (GROSS MWe) 1100 !;

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.7. Maximum Dependable Capacity (Net MWe) 1060 -----~------------------

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0. If Changes Occur in. Capacity Ratings (Items no. 3 thr Since qi j Last Report Give Reasons ________.._____________________ough 7)

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9. Power Level To Which Restricted. If Any (Net MWe) ____

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10. Reasons For Restrictions. If Anys___

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This Mo.

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11. Hours in Reporting Period 744.0 8784.0 61368.0

12. No. of Hrs. Reactor Was Critical 335.3 5294.8 43080.0 pg jr'

13. Reactor Reserve Shutdown Hours 0.0 0.0

~^ 0.0 i ;.

14. Hours Generator on Line 334.7 5198.7 41978.8 pidi$}y

15. Unit Reserve ~ Shutdown Hours O.O 0.0

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, 16. Gross Therm.. Energy Gen. (MWH).

1059199 17028939 133078061' a

17. Gross Elect. Energy Gen. (MWH) 353070 5558820 43785430

18. Net Elect. Energy Gen. (MWH) 340496 5364363 42217734 Tj

19. Unit Service Factor 45.0 59.'2 70.8

20. Unit Availability Factor 45.0 39.2 70.8

21. Unit Capacity Factor (MDC Net) 43.2 57.6 67.7 SNk

22. Unit Capacity Factor (DER Net) 41.6 55.5

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23. Unit Forced Outage Rate 0.0 3.9 12.7 1

24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):.

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[s_t_ iga (e_d_ja(e,_of_st_ar(up,g,janua_g,11, 1985. ' Estimated Date of Startup

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26. Units in Test Status (Prior to Commercial Operation):

Forcast Achieved G1 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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_ 2 IlNIT SiltilDOWNS AND POWER RElbllCTIONS UNIT NAblE D.C. Cook Unit DATE 1-5-85 COMPLETEp my B.A. Svensson HLPORT AIONTil December, 1984 616/465-5901 TELEPik)NE PACE 1 of 2 E

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HH HTEXCH Reactor power reduced to 58% to per-mit removing the east main feed pump from service to check the F-P Turbine Condenser for tube leaks. Three leaking tubes were plugged. Reactor power was returned to 100% on 841208.

155 841208 F

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4 N.A.

HH HTEXCH Reactor power reduced'to 53% to per-mit removing the east main feed pump from service to check the F-P Turbine i

Condenser for tube leaks. One leak-ing tube was plugged. Reactor power was returned to 100% on 841209.

156 841213 S

433.3 S&F.

1 N.A.

ZZ ZZZZZZ Started a power reduction to 57% in preparation for the scheduled ice condenser surveillance outage.

Re-actor power was held at 57% until 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> on 841214 when power re-duction was resumed to remove the Unit from service.

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lixlobit G. histanctiivis S: SilicJuical A Espispmes-i Failine(Explain)

I Manual fin Pseparatism of Data 11 Maintenance ni Tcat 2 Manual Scrani.

Enity Sheets foi 1.icensee C-Refueling 3 Automatic Stram.

Event Repus (l.l:R) File INilRI:G-D Regulaansy Ressiiciiim 4-Othes (Explain) 016li IM)pesanos Isausing a license I:xaminaliens F Adminisisasive 5

G Opesatiimal 1:ssus (Explain) lislubit I Same Somce t9/1i) 11 Othes (Esplaini

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UNIT SHUTDOWNS iND POWER REDUCTIONS INSTRUCTIONS This report should descrce all plant shutdowns during the in accordance with the table appearms on the report form.

report penod. -In addiuon. it should be the source of explan.

If category 4 must be used. supply brief comments.

anon of signiacant dips :n average power leveis. Each sign >

ficant reduction in power level (peater than 20'e reduction LICENSEE EVENT REPORT z.

Referen:e the applicable in averig daily power leve! for the precedmg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertammg to the outage or power should be noted, sven though the unit may not have been reduction. Enter the Ern tour parts (event year. sequencal shut down completely. For such reductions in power level.

report number occunence code and report type) of the tive l

the duration should be listed u :ero, the method of reducuan pan designation as descnbed in item 17 of Instruccons for should be listed as 4 (Oder), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREC.0161). This information nsay not be Cause and Corrective Acuon to Preveht Recurrence column immediately evident for all such shutdowns, of course, smee should be used to provide any needed explanation to fuily further invesugation may be required to ascertam whetur er desenbe the circumstances of the cutage or pcwer reduction.

not a mporuble ec:urrence was involved.) If the u. age or power reducuon will not result in a reportaofe es:urrence.

NUMBER. This column should indicate the sequential num.

the positive indication of this Isck of correlation should be ber assigned to each shardown orsigmAcant reductionin power noted as not applicable (N/A).

for that calendar year. Wl en a shutdown or sigmacant power SYSTEM CODE. The system in which the outage or power reduction begms in one report petiod and ends in another.

M MNh by da m'HO ch' an entry should o, e made for both report penods to be sure all shutdowns or signalcant power reductions are reported.

Exhibit G. Instrucuans for Preparation of Data Entry Sheets Until a unit has achieved its first power generation. no num.

for Licensee Event Report (LER) File (NUREG.0161).

ber should be ass gned to each entry.

Systems that do not fit any existing code should be dengna.

ted XX. The : ode ZZ should be used fer those events where DATE. This column should indicate the date of the start a system is not appli:able.

of each shutdown or signiikant power reducuo6. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Sele:: the most appropriate component as 00314. When a shutdown or ugnificant power ceducten from Exhibit !. Instruenons for Preparanon of Data Ent )

begmsin one report pened and ends m ancther, an entry should Sheets for Liesnsee Event Report (LER) File (NUREG.0161).

be made for both report penods to be sure all shutdowns using de following entiena:

or significant power reductions are reponed.

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

duied." respe:tvely, for each shutdown or signiBcant power B.

If not a component fat!ure, use the reisted component reducuan. Fcrcad shutdowns incluce dose required to be e.g.. wrong valve operated through erron list valve as

mtisted by no later than the weekend following discovery -

component.

of an off.norrnal condinon. It is recognized that seme judg.

ment is requ: red in :stegotiz:ng shutdowns in this way. In C.

If a chain of failures occurs, the Sist component to mai.

general, a fo:ced shutdown is one that would not have been-function should be listed. The seouence of events. includ.

completed in the absence of the concinon for which corrective ing the other components which fait should be descnbed action was tr. ken.

under the Cause and Correcuve Action to Prevent Re:ur.

rence column.

DURATION. Self-explanatory. When a shutdown extends eeyond the end or a report penod, count only the ume to the Components that do not St any existmg : ode should be de-ugnated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensumg down tme in the foilswmg recort penods. Report duratton of outages events where a component dengnation :s not applicaole.

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

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

the sum Jr the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fashion to ampiify or tor was e n line should equal the gross hours in the reportmg explain the circumstances of the shutdown orpower reducton, penod.

The column shoulc include the soectSc :ause for each shut.

wn or nan ant p wn m un n and de immedate anc REASON. Categonze by letter destynation in accord $nce

• tth the table appearmy un the repon form. If :stegory H eentemolated long term ectrecuve scuon taken. if appropn.

ste. This column should siso be used for a descnotion of tne must he used, supoiy bnet comments.

ma or safety related corrective mamtenance performed dunna de

\\tETHOD OF SHUTTI.NG DOWN THE RIACTOR OR utage or e we mdunon inc!uding an idenuncation ot; REDtXING POWER. Categonze ey numner desgnacon

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radioseunty or angle radianon exposure spectuca INote that mis differs trem the Ecison E!es:n: Insuture sted with the outage wiuch accounts for more than 10 :ercent i EEI) letimtions of " Forced Pantal Outage" and -Sene, of the allowacle annuai values.

Juled I^artial Octag." For these terna. i El uses 4 Jange or For long textual recorts contmue narrative on separate ; aper

.t0 MW as the breax ;wnt. Fur :arger power resiitors.30 MW 2nd reteren.e the shutdown or power reduonun for tna

s in. imail a shange tu wanut espianation.

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I)OCKET NO.

UNIT N AblE D.C. Cook Unit 2*

tlNIISiltilllOWNS ANilPOWER REDIMTIONS ilATE 1-5-85 COhlPl_ETEll NY B.A. Svensson December, 1984 l

REPORT hlONTil TELEPilONE 616/465-5901 PAGE 2 of 2

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• L Causc & reniccaive Acti4ui to No.

Date Q

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vO t-6 Unit removed from service at 2239 156 hours0.00181 days <br />0.0433 hours <br />2.579365e-4 weeks <br />5.9358e-5 months <br /> on 841214. The Reactor Cool-(Contirued) ant System was subsequently cooled down to Cold Shutdown conditions, Mode 5, and later drained to half loop to permit replacement of RTD Loop Manifold valves. The RCS remain-ed in Mode 5 at the end of the month.

2 3

4 1:: l'osced Heason:

bleiluml; Exlubia G-Instinctionis S: S hednic.I A lialnipinesis I;ailine(lixplain) 1 klannat fo Psepasaiiini of Data ll-klaintenance oi Test 2 klanual Scrani.

Ensiy Sheets fus I.icensee C Hefueling 3 Antonialic & sam.

liven Repens ll.ERIl'ileiNilRIE D Hegulatoiy Hesteiction 4 Othes (Explaial 0161)

!! Opciatos Isaining a license 1:xamination 1: Adminissiative 5

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UNITSHUTDOWNS AND POWER REDUCTION $f INSTRUCTIONS This report should descr e all plant shutdowns'during the in accordance with the taole appearing on the report form.

report period. In addition.it should be the source o(explan-If category 4 must be used, supply brief commentL ation of signadcant dips m 2verage power levels. Each signi.

ficant reduction m power level (greater than 20% reduction LICENSEE EVENT REPCRT z.

Reference the applicable m average daily power level (cr the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) mportaole murrence pertauung to the outage or power should be noted. even dough the unit may not have been mduction. Enter the Erst four pans (event year. sequennal shut down completely. For such reductions in power level.-

report number, occurrence code and report type) of the tive l

the duration should be listed as zero, the method of tsduction pan designation as desenbed in item 17 ofinstructions for should be listed as 4 (Other). sad de Cause and Corrective 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 Acnon to Prevent Recurrence column immediately evident for all such shutdowns or, course, since should be used to provide any needed explanation to fully further mvesugation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction.

not a reportable cccurrence was involved.) If the outage or power reduction will not result in a reponable occurrence.

NUMBER. This column shculd indicate the sequential num, the posinve indication of this lack of correlanon should be bet assigned to each shutdown or signincant reductionin power noted as not applicab!e (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. T5 e, system in which the outage or power t

reduction begms in one report pened and ends m another,

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reduction originatec should be noted by the two digit code of sn entry should be made ror both report penods to be sure 211 shutdowns or signalcant power reductions are reported.

Exhibit G Instrucuans for Preparatien of rista Entry sneets Until a unit has schieved its first power generstion no num.

for Licensee Event Report (LER) File (NUREG.0161).

ber should be asstgned to each entry.

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Systems that do not fit any existing code should be designa.

4 ted XX. The ecde ZZ should be used for those events where DATE. This column should indicate the care of the start a system is not applicaole.

of each shutdown or signincant power reduccon. Report as year, month. 2nd day. August 14.197 would be reponed.

COMPONENT CODE. Select the most apprepnate component as 70814. When a thutdown or significant power reductton from Exhibit I Instruenons for Preparanon of Data Ent:5 begmsin one report penod :nd ends m another, an entry should Sheets for Licensee Event Report (LER) File (NCREG.0161).

be made for both report penods to be sure all shutdowns usms the followmg entienst or ugruficant power reductions are reported.

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

duled." respectively, for each shutcown or signidcant power B.

If not a component fat!ure. use the related component:

reducuan. Forced shutdowns include those required to be e.g., wrong valve operated through erron list valve as imusted by no later than the weekend following discovery component.

of an off. normal condinon. It is recognized that some judg.

ment is regtured is 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.

ccmpleted in the absence of the condition for which correccve ing the other components which fail, should be desenbed action was taken.

under the Cause and Corteenve Action to Prevent Recur.

tence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end or 2 report penod. count only the tune to the Components that do not St any existmg code should be de.

ugna'ted XXXXXX. The code ZZZZZZ should be used for end or the report penod and pick up the ensuing down time m the following report penods. Report duratson of outages events where a component designation is not appilcaole.

ruunced to the aestest ienth of an hour to fact!Itate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

1 tor was on !ine snoula ecual the gross hours in the reportmg RENCE. Use the column.a a narrative fasinon te ampitfy or penod.

explaan the circumstances of the shutdown orpower reduenon.

The colmnn should include the specinc cause for each shut.

REASON. Categortee by 'etter deugnation in accordance down or signiric.nt power reduction and the immediate anc with the taole 2opeututy on the report form. If category H contemolated long term correenve scuon taken, if appropn.

must he used succiy brtet eumments.

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 p wer reduction including sn identulcation of

'"' 'U"'*I E**h**"}*"#*I'E""I*^Y**bN***#'

l REDUCING POWER. Categonze ov numner desgnanon r:dioacnvity or smgfe tsdzancn exposure speettlesily associ.

INote that this differs trom the Edison Electne Insnture sted with the outsae wtuca accounts for more than 10 cercent iEEll detinutons of -Forced Parnal Outage" and -Sene.

Of the 2ilo*acie 2nnuai values.

Ouled P:rtial Outage. For these temn. EE! uses a shange or For long textus 1 recorts eentmue narrative on secar:re ; scer

'0 MW 25 the breau ;mmt. For larger power resetors. 30 MW nJ reference the shutdown or. power redu nun foi tna

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Docket:No.": E50-316 Unit Nnmas.'D.C. Cook Unit"2 4

Completed By:

A.1S.'Puplis

. Telephones (616)1465-5901 Date: ' January 2,-1985 Page:

1 of 2-

- MONTHLY' OPERATING ACTIVITIES - DECEMBER,'1984

+

' HIGHLIGHTS:'

The - Unit entereld the reporting period in Mode 1 a't.100%

rated' thermal power.

' Major power reduction occurred'to remove 1the "E" Main Feed Pump.

-Turbine. Condenser from service for tube 1 inspection.

The Unit was shutdown on December 14, l'984 for a scheduled.

surveillance outage.- The reactor coolant-system was subsequently drained to half. loop to permitereplacement'of RTD manifold

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isolation-valves.

The Unit remained in Cold Shutdown, Mode 5, for-the remainder'of

the reporting period.

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

SUMMARY

12-7-84 At 1600 Reactor: power-was decreased to'58% to remove the "E" Main Feed Pump Turbine Condenser from service for tube leak inspection'.

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12-8-84 At 0500 Reactor power being increased to 100% wh'ich was reached at 1240 on 12-8-84.

12-8-84 At 1948 Reactor power was decreased to 53%-to remove the "E" Main Feed Pump from service.

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12-9-84 At 0308 Reactor power being-increased to 100% which was reached at 1242 on 12-9-84, 12-13-84 At 2205 Reactor power was decreased to 57% in preparat' ion for the scheduled surveillance-outage.- AT 0210 on 12-14-84, the Unit reached.57% and 650 megawatts..

12-14-84.At 2020 controlled shutdown was commenced to bring:the

-Unit to-coldi hutdown, Mode 5.

s 2239:

Unit removed from service 1

2309:

Reactor in Mode 2 2318:

Reactor'in Mode 3 1

12-15-84 0245:

Degasing of reactor coolant system started.

0330:

-Plant cooldown initiated I

.0848:

Mode 4 entered 2146:

Mode 5 entered i

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. ~,

'Dockst No. ~

50-316-Unit'Nams:

D.C. Cook Unit 2 Completed By:

A. S. Puplis Telephone:'

(616). 465-5901 Date:

January 2, 1985 Page:

2 of'2.

12-23-84

'At 0203 Train B Containment Purge isolated automatically due to Radiation Monitor ERS 2401 spiking.

NRC notified of automatic Engineered Safety Features Actuation.at 0258.

12-23-84 At 0949 Train A Containment Purge isolated automatically due to high, alarm on Radiation Monitor ERS 2301.,.NRC notified of automatic Engineered Safety Features Actuation at 1230.

12-23-84 At 1632 the reactor-coolant system was returned to Hot Shutdown conditions, Mode 4, with Reactor Coolant System heat up in progress.

12-24-84 At-0415,_the reactor coolant system entered Hot Standby conditions, Mode 3.

12-24-84 At 1905, the reactor coolant system was being cooled down and entered Mode 4 due to a leak on reactor coolant loop 4, RTD manifold return isolation valve RC 107-4 which was identified on the containment closecut inspection.

12-25-84 At 0310 the reactor coolant system entered Mode 5 and remained in Mode 5 at the close of the reporting period.

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 system remains m

operable.

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i' DOCKET NO.

.50 - 316 UNIT NAME D. C.-Cook - Unit No. 2 DATE l-4-85 COMPLETED BY B. A. Svensson TELEPHONEL (616) 465-5901 PAGE l of 1.

MAJOR SAFETY-RELATED MAINTENANCE

-DECEMBER,_1984

- M Safety Valve SV-14 on_the. West _ Containment Spray Heat Exchanger-was removed fo'r repair _ due - to leak-by.- The seat _and disc.were

-lapped.and the valve reassembled and returned to service. Cor-rect set. point of the repaired valve was verified.

M-2 Pressurizer Power _ Operated Relief Valve NRV-153 was rebuilt toc eliminate seat leakage. Post-repair retesting verified valve operability.

M-3 Installed new starting air cylinder operator on 2-CD Diesel starting air valve XRV-227. Post-repair functional testing verified new installation operability.

M-4 RC-107-L4, R. C. Loop 4 RTD loop. return isolation valve was-isolated by freeze sealing to facilitate repairs of a body / bon-net leak. RC-107-L4 was disassembled, cleaned, internals in-spected, and reassembled utilizing a new bonnet gasket. Severe corrosion of the carbon steel studs was found.

C&I-l ERS-2300 pump could-not be turned off. Improper operation of the solid state relay that controls the pump relay. caused the pump relay's contacts to weld together. Contacts were separated and burnished-and the solid state relay was replaced.

C&I-2 The loop 3 cold leg wide range RID failed high. A new RTD was installed, and the leop recalibrated.

e

,wlNDIANA & MICHIGAN ELEMRIC COMPANY oonald C. Cook Nuclear Plant P.O. Bom 458 Bridgman, Mchigan 49106 January 4, 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 December, 1984 is submitted.

Sincerely, t) )

W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger B. H. Bennett P. D. Rennix J. H. Hennigan Z.

Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department 9

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