ML20087M671

Monthly Operating Rept for Feb 1984

ML20087M671
Person / Time
Site:	Cook
Issue date:	02/29/1984
From:	Gillett W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8403300157
Download: ML20087M671 (10)

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AVERAGE DATLY UN1T POWER LEVEL m

00CXET NO.

50-315 UNIT 1

DATE 3-6 -84 CCMPLETED BY W.

T. Gillett TELEPHONE 616-465-5901 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 702 17 101s 2

593 18 1013 3

605 19 1013 4

603 20 1012 5

603 21 1013 6

402

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22 1014 7

464 23 1012 8

602 24 1012

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9 700 25 1013

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10 984 25 1013 11 990 27 1017 12 1004 28 1026 13 1007 29 1027 14 1015 30 15 1017 31 16 1017 INSTRUCTIONS On this famat list the average daily unit power level in MWe-Net for each day in the reporting month.

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DOCKEI NO. 50-315 3

UNil'SilOTDOWNS AND POWER REI)UCTIONS uni l' N AME D.C. Cook - Unit 1 DATE 3-8-84 FEBRUARY, 1984 COMPl.ETED itY B.A. Svensson HEPOR I MONIll TEl.l:PilONE 616/465-5901 PAGE 1 of _2 e.

f*l 33 3

N' I icensee

$ 8,,

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Cause & Conective No.

Date Q

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Auson to liven Fy fI 3 ;g g itepius #

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Pievent Hecumence t-O e

O 212 840201 F

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4 N.A.

Cll PUMPXX A power increase from 79% to 99% was in progress when at 93% the West main feed pump, MFP, developed a vibration problem. A power reduction to 59%

was started immediately to remove the West MFP from service.

213 840206-F 7.0 A

1 N.A.

Cil llTEXCll While the West MFP was still out of service, the East MFP turbine conden-ser developed a condenser tube leak.

To effect repairs, the Unit had to be removed from service. The reactor was maintained critical at 6% power.

One leaking tube was identified and plugged. The East MFP was returned to service the same day and the Unit paralleled to the System on 840207.

Reactor power was increased to 61%

where it was held pending completion of the W MFP repairs.

I 2

3 4

F: Fo ced Reason:

Meiln><l:

Entobin G-Insieuctions S: Scheiluleil A l?ttuipment Failme(l;xplain) 1 Manual fin Psepasation of Data ll Maintenance of Test 2 Manual Sciam.

Ennay Shee:S fue 1.icensee C Refueling

.l Automatic Scsam.

livens Itepou ll.l:R) File INilRI'G-D HegulalOly NCstlicliun

• l-Othel ( ExplJin) 01(#1 )

li-Opesanos Tsaining & license 1 xamination F Aihninist:ative 5

G-Opeiational Luos Ilixplam)

Inhibit 1 - Same So.nce 19//7)

Il Othes (lisplain)

.m.

UNIT SHUTDOWNS AND POWER REDUCTIONS l

l INSTRUCTIONS This report should deser e a!! plant shutdowns during me

n accordance with the table appeanng on the report form.

report penad. In addition. It should be the source of explan.

If category 4 must be used. supply brief comments.

anon of significant dips m average power levels. Each stani.

ficant reduenon in power level (greater than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable

~

in average daily power leve! for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertainmg to the outage or power should be noted, even thouch the unit may not have been reduction. Enter the first four parts (event year. sequenna!

shut down completely. For'such reduccons in power level.

report nurnber, occurrence code and report type) of the rive l

r tne duration should be listed as zero, the method of reduction part designation as desenbed in item 17 of Instruenons for should be listed as 4 (Other), and the Cause and Correenve Preparauon of Data Entry Sheets for Liceitsee Event Report Acnon to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause and Correcdve Action to Prevent Recurrence column immediately evident for all su h shutdowns, of cou se, smee g

should be used to provide any needed explanation to fully rurther mvesugation may be required to ascertain whether or desenbe 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.

NUMBER. This column should indicate the sequential num.

the positive indication of this lack of correlation should be 3

ber assigned to each shutdown orsigmdcant reduction m power noted as not applicable (N/A).

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

reduction onginated sh' uld be noted by the two digit code of o

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an entry should be made tor both report periods to be sure i

all shutdowns or signtdcant power reducuens are reported.

ExWt G. Instmedons for Preparaton of Data Entry Sheets Unt:1 a unit has achieved 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 existmg code should be designs.

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 applicaole.

of each shutdown or signtiicant power reduction. Report as year. mcnth, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770514 When a shutdown or significant power reduction from Exhteit !. Instructions for Preparanon of Data Ent:3 i

begms m one report pened and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

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

or sigmilcant power reduedons are reported.

TYPE. Use "F' or "S" to indicate either " Forced" or " Sche-da!ed." respectively, for each shutdown or significant power B.

If not a component failure, use the related component:

reduccon. Forced shutdowns include those required to be e.g., wrong valve operated through error: list valve as mitiated by no later than the weekend fo!!owing discovery component.

of an off.nomial condiuon. It is recognized that some judg.

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

If a cham 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 fall 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 of a report penod, count only the time to the Components that do not fit any existing code should be de-end or the report period and pick up the ensumg down time signated XXXXXX. The code 777777 should be used for m the following report penods. Report duranon of outages events where a component designation is not spplicable.

~

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

The sum of the total outage hours cius 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 fastuon to amplify or pen d.

explam the circumstances of the shutdown orpower reducuon.

The column should include the specific cause for each shut.

REASON. Categonze b3 letter deugnanon in accordance down or sigmficant power reduction and the immediate and-with the table appearing on the report form. If category H contemplated long term correenve action taken, if appropn.

must be used.suppiy bnet comments.

are. This column should also be used for a desenption of the major safety.related corrective maintenance performed dunng METHOD OF SHUTTING DOWN THE REACTOR OR the outsee or power t' eduction including an identification ot; REDUCING POWER. Categonee by number designation the entical path activity and a report of any smgle release et radioactivity or single radiation exposure speettleaily assoet.

INote that this difters trom the Edison Electric Insnture sted with the outage which accounts for more than 10 percent -

EEI) detinttions of " Forced - Parnal Oursee" and " Sche, of the allowabic annual values.

duled P:rual Outage." For these tenn>. EE! uses a shange or 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 redusuun for this

)

is em small a whange to wanant esplanation

. narranve.

W77 v..-

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50-315 DOCKETNO.

tJNIISilUTDOWNS AND POWEll HEDtiC'llONS UNIT NAblE D.C. Cook - Unit 1 DATE 3-8-84 COblPLETED llY B.A. Svensson HEPOR I AIONI'll FEBRUARY, 1984 616/465-S901 lEl.LPilONE PAGE 2 of 2

t.

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I, Cause & Conective No.

Date g

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j;Eg Repost #

8E 0 Prevene itecurrence H

6 213 (C intinued)

Inspection of the W MFP revealed in-dications of rubbing between the outer impeller hub and the diaphragm wear ring. The pump was. returned to service on 840209. Reactor power was increased to 95% the same day.

Re-actor power was increased to 98% on 840213 and 99% on 840227.

I 2

3 4

1:: Forced Reason:

hiethixt:

Exinbii G - Instiuceions S: Stheduled A-Equipment Fashne(Explain) 1 klannal for Psepaiation of Data li-Maintenance of Test 2 Manual Scram.

linisy Sheets for 1.icensee C Refueling 3 Automatic Scram.

Event Repoolll.liR)1ile INtlRI:G-D Regulaeony Resisiction 4-Othes (lixplain) 0161) li-Opesatin liaining & License lixamination 5

12-Adminisitative.

G Operational Enor IExplaial lislobis 1 - Same Somce 01/77) 11 Olhes (fixplain) -

j

<a.

l 1

1 UNIT SHUTDOWNS AND POWER REDUCTIONS i

INSTRUCTIONS j

This report should desenbe all plant shutdowns during the

n accordance with the table appearms on the report form.

report penod. In addition. tt should be the source of explan-If category 4 must be used. supply bnef comments.

anon of signiHcant dips m average power levels. Each s2 ni-Scant reducuan in power level (greater than 20"e reduction LICENSEE EVINT 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 />) reportable ocettrence pertaming to the outage or power should be noted, even thoud de 2 nit may not have been reduction. Enter the nrst four parts (event year. sequent:a!

shut down completely. For'such reductions m power level, report number, occurrence code and report type) of the nve l

the duration should be listed as zero, the method of reducuon part desipation :s desenbed in Item 17 of Instructions for should be listed as 4 (Other), and de Cause and Correcuve Preparanon 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 Acuan to Prevent Recurrence column immediately evident for all such shutdowns, of course, smee should be used to provide any needed explanation to fully rurther investigation may be reqmred to ascertam whether or desenbe the circumstances of the outage or power reduction.

n t a reportabz,e occurrence was involved.) If the outage or power 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 sigmHcant reductionin power n ted as not applicable (N/A).

for that ealendar year. When a shutdown or s2gmHcant power SYSTEM CODE. The system in which the outage or power reducuon begms in one report pened and ends m another, an entry should be made tor both report penods to be sure reduction onginated sh'ou!d be noted by the tw"o digit eode of all shutdowns or sig:uncant power reductions are reported.

Exhibit G Instrucuons for Preparation of Data Entry Sheets Until a unit..as achieved its first power generation, no num-for L:censee Event Report (LER) File (NUREG-0161).

ber 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.ndicate de date of the start a system is not applicable.

of each shutdown or sigm$ cant power reducuan. Report as year, month. and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropnate component as 770314 When a shutdown or sigmEcant power reduction from Exhibit i. Instrucuans for Preparanon of Data Entry begms m one report pened and ends :n 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 entiena:

or sigmncant power reductions are reported.

TYPE. Cse "F" or "S" to indicate either " Forced" or " Sche-duled." respectively, for each shutdown or signincant power B.

If not a component failure, use the related component:

reduction. Forced shutdowns include dose required to be e.g., wrong valve operated through erron list valve as initiated by no later than de weekend following discovery component.

of an off. normal condition. It is recognizeu 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 Corrective Mtion to Prevent Recur.

rence column.

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

end or the report penod and pick up the ensuing down time signated XXXXXX. The code 777777 should be used for in 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 facilitate summation.

The sum of the 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 fastuon to ampiify or pen d.

explam the circumstances of the s'tutdown or power reduction.

The column should include the speciSc cause for each shut.

REASON. Cateaunze by letter deugnation in accordance down or significant power reduction and the immediate and with the table appearing on the report form. If category H contemolated lone term corrective action taken, if appropn.

must be used. supply brief eumments.

ate. This column'should also be used for a desenption of the major safety.related corrective rnaintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR ' OR the outage or power reduction including an identification of REDUCING POWER. Categonze ey numner designation the entical path acuvity and a report of any sinele release et radioactivity or smgle radiation exposure spectrically associ.

INote that this differs trom the Edison Electric Institute sted with the outage which accounts for more than 10 percent-tEEll detinitions of " Forced Partial Outase" and " Sche.

of the allowable annual values.

Juled Partial Outage." For these tenn3. eel uses a shange or For long textual reports continue narrative on separate paper J0 MW as the break pomt. Fur larcer power reactors.30 MW and reference the. shutdown or power redustion for th;>

ts im small a change to wanant oplanation.

narranve.

(9'77

___mqf.,.

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a.Aa.g-

f Docket No.:

50-315 Unit Name D.C. Cook Unit 1 Completed By:

G. J.

Peak Telephone:

(616) 465-5901 Date:

3/8/84 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - FEBRUARY 1984 Highlights:

The Unit entered the reporting period in Mode 1 holding at 79% of rated thermal power due to secondary side chemistry requirements.

During the subsequent power increase problems developed with both Main Feedpumps and they had to be removed from service.

The Unit was divorced from the Grid and the reactor was held at low power while the feed pumps were repaired.

The Unit was then loaded to 99% of rated thermal power and held there due to the allowable power limit restriction for the balance of the reporting period.

Total electrical generation for the month was 637,460 MWH.

Summary:

2/1/84 Power was increased to 93% at 1140.

Power was reduced to 59% at 1258 to remove the West Main Feedpump from service due to high vibration.

2/2/84 AB Diesel Generator was inoperable from 1638 on 2/2/84 to 2322 on 2/4/84 due to low lube oil viscosity.

2/6/84 Reactor power was reduced to 6% and the Unit was divorced from the Grid at 1737 hours0.0201 days <br />0.483 hours <br />0.00287 weeks <br />6.609285e-4 months <br />.

The East Main Feedpump was removed from service at 1831 to repair a condenser tube leak.

2/7/84 The Unit was paralleled to the Grid at 0038-hours.

A power increase was started-after the East Main Feedpump was returned to service.

Power reached 61% at'lll5 and was

~

held there pending repairs to the West Main Feedpump.

2/9/84 West Main Feedpump returned to service and a power increase started at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />.

2/11/84 Power reached 97% at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> and was held'there due1to the Allowable Power Limit Restriction.

2/13/84' The Allowable Power Limit was raised and power was increased to 98% at 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />.

2/17/84 Reduced power to 97% for turbine valve testing and then increased back to 98%.

2/27/84 The Allowable Power Limit was raised and power was. increased to-99% at 1724 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.55982e-4 months <br />.

~.

s '

Docket No.:

50-315 Unit Namn D. C. Cook Unit 1 Completed By:

G. J.

Peak Telephone:

(616) 465-5901 Date:

3/8/84 Page:

2 of.2 I

i Train A of the Containment Hydrogen Monitoring System remains inoperable as of 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on 2/22/84.

Train B of the Containment Hydrogen Monitoring System' remains operable.-

The Control Room Cable Vault Halon System remains inoperable as of 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 4/5/83.

The backup CO System for the Control Room 2

Cable. Vault remains operable.-

i i

e 1

J G

8 A

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.N, t

-DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No'. 1 r

DATE 3-8-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 4

PAGE 1 of 1 i

MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1984 i~

M-1 The lube oil viscosity of the AB Emergency Diesel was low.

Replaced four fuel pumps and one fuel injector. Replaced i

all of the lube oil and had the engine tested.

~

M-2 Unit 1, AB Diesel Starting Air Compressor #AB2 was leaking oil. A rebuilt compressor was installed. Testing was per-formed and the compressor was returned to service.

C&I-l Reactor Coolant System loop 2 flow channels 1-NFP-221 and 1-NFP-222 had a 3% deviation between.them. Foxboro trans-mitters NFP-211~and NFP-222 were calibrated,. eliminating the i

-I 3% deviation.

C&I-2 Steam Generator #2 power operated relief valve, MRV-223, opened spuriously when in the " automatic" mode.. The valve positioner.was exercised and the limit switches were adjusted.-

The. positioner relay. appeared to have been plugged with dirt.

After the dirt was blown out, the valve was successfully

. cycled.

i C&I-3 Delta T/auctioneered AT deviation low alarms annunciator; alarmed ' periodically for no apparent reason.with no change-in:other'AT instruments.

"High'AT" select module-TY-411H

.was found to be'at fault. The module.was replaced.and was

~

calibrated.

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~~,5 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 March 8, 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 Feburary,1984 is submitted.

Sincerely, Q),/

W. G. Smith, J/.

Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich I

R. W. Jurgensen hTC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center

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