Text

Monthly Operating Rept for Oct 1982
	ML20071Q773
Person / Time
Site:	Cook
Issue date:	11/02/1982
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20071Q754	List: ML20071Q751; ML20071Q773; ML20071Q791; ML20071Q814;
References
	NUDOCS 8212290424
	Download: ML20071Q773 (8)
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OPERATING DATA REPOPJ 4.s..-

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50-315 DOC:GrNo.

DA73 11-2-82 COMP 1.ETIO EY W. T. Gillett -

TELIPHONE 61AdA4Ep01 o???.AT'NG S- ; TUs Donald C. Cook 1

Not:5 g, egg y,,,.

2. Report:s;? ded: October 198p

3. U~W Th :=:1?ower (MWt):

3250 1089

4. Ns=eplais Rada;(Cross MWe):

1054 S. Desi;n Ele =d=l as:in;(Nec 51We):

1080

6. M:::i=un: Depend hls Cavachy (Cross 51We):

1044 T. M= rim.m Dep-d '! C:::chy (Net MWe):

S. If Curr;es Cc=rin CapacLy R::i:;s (1: =s Number 3 Th:ou;h 7) Sine: Las: Repor:. Give R:ssons:

9. hower Leve! To Whi=h Res: dead. If Any (Net MWe):

10. R sons For ?- tri: dons.lf Any:

This Month Yr.<o.Cata Cu=u!:tive 745 7.296 6R.664

11. Hours In R:;ords; Pedad 716.2 4.144.4 50.417.6

12. Nu=h:r Of Hou:s R==:ce Was Cdd=1 463

13. Re:c:ct Rese.ve Shn:down Ho.::s

14. Hours Gen r-:se Cn Une 711,4 4.026.7 49 ?49.4 321

15. Ud: R.-serve Shu:down Hou=

1,965.827 J2,483,644 142.846.833

16. Cross Thc=.! En :;y Cen==: d (MWE)

17. Cross Elec:.=1 Eser;7 Cent::: d I.M W H) 637.410 _

4,093.980 46,975.760 611,608 3,946,712 45.187.390

13. Net E!:=d=1 En=r;y Gene =: d (MWE) 95.5 55.? -

73.9

19. Unit Servi = F:: tar 95.5 55.2 73.9

20. Uc:t Ar.ilabilky F:c:or 78.6 51.8 66 7

21. Uni: C:paci:/ :":::er (Usin; MDC Net) 77.9 51.3 61 5

22. Unit Capscity. :::or (Usin; D ER.4et t 4.5 E3,,,

99

23. Unit. core:d Cu::ge R:c,

24. Shutdowr.s Scheduled Over Nec 5 Mon:hs (Type. 0:te.:nd Du:: don of Z:cht:

5. If Shu: Down At End Of R:-ort P::fod. I:ti==:ed D:te af sta-:ue:

. 5. Units !n Tes: 5:::us iPrior ta Ce=== :is! Open:fon1:

Fore =st Achieved INITIA L CRIT *CAUTY

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INITIAL II.ICTR:C;W C o.*.:MIT.C:A '. 0 ? IRA T:ON 8212290424 821112 i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-315 UNIT I

DATE 11-2-82 COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH October l'982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 0

17 1037 2

182 18 1028 3

404 19 1032 4

409 20 1034 5

509 21 1030 6

658 22 1020 7

725 23 600 8

869 24 1018

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9 961 25 1005

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10 1003 25 539 11 1015 27 531 12 1031 28 640 13 1030 29 1018 14 1035 30 1027 15 1034 31 988 16 1026 INSTRUCTIONS On this femat list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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llNIISilulDOWNS AND POWElt HLDtlC~llONS C

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An g DAIE 11-12-82 i

B.A. Svensson October,1982 COkiPi tflEin itY 1(I POR l' hlON ill 1El.LPilONE 616-465-5901 PAGE 1 of 1 h3

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186 820930 S

33.6 B

1 N.A.

ZZ ZZZZZZ Unit was removed from service on 820930 for turbine overspeed testing and to repair body-to-bonnet leak on pressurizer auxiliary spray valve, QPN-51. The unit was returned to service 821002, and the power esca-lation testing program was commenced.

100% reactor power was reached on 4

821011. Total length of the outage was 45.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

187 821023 F

0 B

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 55% to re-move the West main feedpump turbine from service to repair leak in the hydraulic oil system. Reactor power returned to 100% 821024.

188 821026 F

0 B

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 55% to re-move the West ri,ain feedpump from service to correct high vibration problem on pump outboard bearing.

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-Reaci.ur puwer rei.urned i.u leo %-821029.

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3 1

1:: 1:enccil iteawn:

kle'huil:

Estabis G - lusinicssons S. Silicilnicil A I agnspnici.e I ailnic (l.xplain) 8 Alainial fin Psepasasson of Dal.a ll kl.iinicnance or Test 2-klannal Sa.nn.

linny Sliccis fin Iisensee C.iteincling

.l Aniennaisc So.nn.

INeni l<cpiu s il l~lO l'ile INulti G-1 Itegulahuy ite>isia. tion 1 Othen ll'.xpl.nn)

Ult >I) l Opesaios liaining a litense I maininaison i

F Ailuunisuaisve G Opes.siional Iisos (INpl.unt IThilni I - Saine Sinnce es/ / /)

11 Olhes (l%plaini

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Thts report snou'd desenbe 211 plant shutdowns dunng ne m ::::r:an:e with 2e ts:le ap:esnns on se report form.

report pened. In addit:en,it should be the sour:e ciexplan.

If:stegory 4 must be used. suppiy onef::mments.

2non of sigmncant dips :n 2versge power levels. Es:n strat.

nesnt recu:non m pcwer level (grester dan 203 reduction LICENSEE EVENT REPORT =. Reference 2e apph.:::le m 2verage daily power level for the preceding 24 hnurs)

MPC"2CI' CC3f" C' J'".2225 80 d' C"123' C' E0* *j red =nen. :nm de um cur pans Wnt yes:. seventL.

could be noted even though te umt may not have been shut down cornpictely. For sus reductens in ;cwer leve!.

rep rt number a : ::ence =de and re: ort type) of me n,ye l

the durst. ort should be !!sted as zero.the medod of redu uon

2rt designation 2s des: nbed in item I, or Inst uenons ter tLf2 2"Cn of Dats Entry Sheets for L2:ensee Event Re:cr PI' should be listed as 4 (Other),2nd the Cause 2nd Cctre:nve

.R) ru.e tNLRIG.0161). ims :nfor=2 tion may not :e Acuen to.arevent Recurrence :: umn shou.. expiam.

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Cause 2nd Corre:nve Acnon to Prevent Recur:ence column

=med:stely evtdent (cr 21: such shutdowns. of course smee should be used to provide any needed explanation to fully turther mvestgation may be recmted to ascertam whetne; or

.esenbe the :ircumstances of tne outage er power reduction.

not 2 reportable oc:urrence was mvolved.) If the outage or power reducnon wtll not result :n a reportssie oc:urrence.

NU5tBER. This ::iumn should ind!=te the secuential num.

the p sitive mdi:stien of oss !sck of correlst:en should be her assigned to each shutdown or sigmne:nt reduc'nort m power noted as not applic2::e INIA).

for that esiendar year. When a shutdown or s:gmncant power SYSTE31 CODE. The system in whid the outage or power reduetton begins m one report period 2nd ends m 2notner.

reduenen ongmated A' uld be noted by the tw"o digit e:de of o

2n entry should :e mace for botn report penods to be sure c.

Exmost G, Instruences for Prec2rsuon of Data ntry snee s

11 snutdowns or sigmn; ant gower redu:uons are reported.

for L:censee Event Re: ort (LER') File (NUREG.0161).

Lat:12 Urut. 2s 2:Ceved its.. :t power jeneration, no num.

ber should be assigned to each entry.

Systems that do not fit 2ny exisung :cde should :e designa-ted XX. The cce ZZ should be used for dose events where DATE. This column should mdicate de date of de start 2 system is not appli: sole.

of each shutdown or sigmnesnt power reducnors. Report as year. =enth. 2nd say. August 14.1977 would be reported C051PONENT CODE. Sele:t ce mest 2:ptcpr: ate component as 770514. When 2 shutdown or sigmfic:nt power :educnon from Exhibit I. Instruenons for Prep 2:2nen of Data Ent:3 begms in one report pened and ends :n 2noder 2n ent:y should Sheets for Licensee Event Report (LER) F:!c (NCREG.0161 L l

be made for both report penCds to be sure all shutdowns usmg e followmg :Utien2:

or s:gmn:2rit power reductions are reported.

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

duled." respe:nvely. for e:en shutdown or significant power B.

If not 2 :om:enent failure. use de reisted com:cnent:

redu non. For:ed shutdowns m:!ude those requaed to be e.g.. wrong valve operated through error; hst valve as

mtisted by no 12ter than the weekend followmg discovery

omeonent.

cf 2n off. normal condition. It is re: gmzed that some judg.

ment is required in :stegonzmg snutdowns in this usy. In C.

If a : ham of fatlures oc:urs. tne first :omeonent to mai.

general. a forced snutdown is one that would not have been function should be listed. The secuence of' events.mciud.

ecmpleted in de absence of the condition for which :orrectve ing de other components wh::h fail. should be des:nbed scucn was taxen.

under the Cause 2nd Corre:nve Act:en to P: event Re:::.

tence column.

DURATION. Self-ex;ianatory. When a shutdown extends Components that do not at say existmg : ode should be de.

eyond the end or 2 report penod. count only de t:me to the signated XXXXXX. The code ZZZZZZ should be used for 1

end or de re: ort penod and pick up the ensumg down time events where 2 :omeonent designancn is not appii:2:le.

m me :oJowmg re: ort =enods. Report duranon of outages rounded to tne nearest tenth of an hour to fac:litste summatten.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

(

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

RENCE. Use the eclumn :n a narranve fash:cn to ampi:fy or tor was on line should equal the gress hours in the reportmg explam de :::cumstances of the shutdown or power recucnen.

pe nod.

The :clumn snould :nclude the spectne :suse for each snut.

down or siamne:nt power reducnon and the :mmediate anc REASON. Categonee 5.s :etter desynauon m accordance

ntemmsted long term correenve acnon taken. if se roen.

mth tne table a:pearmg on the report form. If :stegory H 3,,

7g3 ;

-should also be used for a desen: tion'ofi.e must 5e used, suppiy $ner comments.

maior $2fety4:!sted ctre:nve maintenance performec dunna METHOD OF SHUTTING DOWN THE REACTOR OR mage or p we reduenen Mudmg 2n Mentuhon y e

O' #U"'s! pam 2emy and 2 repen or any smgie messe n REDUCING POWER. Catemnze ev numre: designanon r:cioactmty or smgle tsdisuon ex:csure s:ee:ne:ily assee:.

1%e snat this differs from t: e Edison E'e:tri: Insutute atec with e out:ge wh :n ae: unts for more inan 10 :ereent t EEll denmuons os " Forced Part:al Outsge" and "Sene.

Jide 2110*2 ie 2nnu2i v2ites-Ju!ed Partial Outauf' For these tenm eel uses a shange or For long textusi reecn> e:ntmue nartsuve on se:arste ;::er

.N) MW as the break punt. For :aryer ; ower reactors. 30 Stw and cereren.4 the snutcown or power recu,::vn no a

.s t..a small a change to wanant oplanation.

narrative.

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Dockat N).:

50-315 Unit Name:

D. C. Cook Unit 1 Complet:d By:

C. E. Murphy Telephone:

(616)_465-5901 Date:

11/10/82 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - OCTOBER 1982 Highlights:

The Unit entered _the reporting period with the completion of repairs to the Pressurizer Auxiliary Spray Valve. Unit heatup from s3680F to s5400F was begun on October 1.

The Unit was paralleled to the grid Lt 0937 hours0.0108 days 0.26 hours 0.00155 weeks 3.565285e-4 months on October 2 and reactor power was escalated to 100%

. power at 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months on Oct. 11. Power escalations during the Nuclear Section testing are addressed in the summary.

A power reduction was started at 2204 hours0.0255 days 0.612 hours 0.00364 weeks 8.38622e-4 months on Oct. 22. The reactor power level of 55% was achieved at 0427 hours0.00494 days 0.119 hours 7.060185e-4 weeks 1.624735e-4 months on Oct. 23. The power was reduced in preparation to the removal. of the West Main Feedpump for repairs to it's Lube Oil System.

Folicwing repairs to the West Feedpump a reactor power increase was commenced at 1910 hours0.0221 days 0.531 hours 0.00316 weeks 7.26755e-4 months on Oct. 23 and 100% power was achieved at 0546 hours0.00632 days 0.152 hours 9.027778e-4 weeks 2.07753e-4 months on Oct. 24.

A reduction in reactor power was started at 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months on Oct. 25 in preparation to again remove the West Main Feedpump, this time to correct a vibration problem. At 0231 hours0.00267 days 0.0642 hours 3.819444e-4 weeks 8.78955e-5 months on Oct. 26, reactor power was lowered to 55% and the West Feedpump was removed from service at 0755 that day.

Following repairs to the West Feedpump, a power increase was started at 1459 hours0.0169 days 0.405 hours 0.00241 weeks 5.551495e-4 months on Oct. 28.

100% power was achieved at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on Oct. 29.

Power reductions for Turbine Valve testing was performed on Oct. 22 and 29. These are addressed in the summary.

The gross electrical generation for the month was 637,410 MWH.

Summary:

10/2/82 Connenced Reactor Startup at 0428 hours0.00495 days 0.119 hours 7.07672e-4 weeks 1.62854e-4 months .

Reactor critical at 0451 hours0.00522 days 0.125 hours 7.457011e-4 weeks 1.716055e-4 months .

Mode 1 at 0631 hours0.0073 days 0.175 hours 0.00104 weeks 2.400955e-4 months .

Unit parellel to grid at 0937 hours0.0108 days 0.26 hours 0.00155 weeks 3.565285e-4 months .

30% power at 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months .

48% power at 1949 hours0.0226 days 0.541 hours 0.00322 weeks 7.415945e-4 months .

10/5/82 68% power at 2038 hours0.0236 days 0.566 hours 0.00337 weeks 7.75459e-4 months and holding for " Moderator Temperature Coefficient" testing.

i 10/7/82 80% power at 1346 hours0.0156 days 0.374 hours 0.00223 weeks 5.12153e-4 months .

l Component Cooling Water System, Train B, inoperable for 19.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months while Maintenance repaired the ESW Cooling Water Outlet Valve on the CCW Heat Exchanger (WM0-737).

Dock:t No.: 50-315 Unit Name: D. C. Ccok Unit 1 Complct:d 8y: C. E. Murphy Telephone: (616) 465-5901 Date: 11/10/82 Page: 2 of 2 10/8/82 90% power at 1513 hours0.0175 days 0.42 hours 0.0025 weeks 5.756965e-4 months .

10/9/82 97% power at 1640 hours0.019 days 0.456 hours 0.00271 weeks 6.2402e-4 months .

10/11/82 100% power at 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months .

10/12/82 South Safety Injection Pump, inoperable for a 93.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period due to excessive vibration. Note: The LC0 time limit was extended for 10 days by the NRC.

10/19/82 West RHR pump was inoperable for a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period for Maintenance to repair an oil leak.

10/22/82 95% power at 2255 hours0.0261 days 0.626 hours 0.00373 weeks 8.580275e-4 months for turbine valve testing.

10/23/82 55% power at 0427 hours0.00494 days 0.119 hours 7.060185e-4 weeks 1.624735e-4 months , to make repair to the West Main Feedpump Lube Oil System.

Repairs completed to the West Main Feedpump at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months .

10/24/82 100% power at 0546 hours0.00632 days 0.152 hours 9.027778e-4 weeks 2.07753e-4 months .

10/26/82 55% power at 0231 hours0.00267 days 0.0642 hours 3.819444e-4 weeks 8.78955e-5 months , to make repairs to the West Main Feedpump, high vibration.

10/28/82 Repairs completed to the West Main Feedpump at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months .

10/29/82 100% power at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

10/30/82 93% power at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months for turbine valve testing.

100% power at 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months .

i i

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 11-12-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1982 M-1 The reciprocating charging pump packing was' leaking.

Replaced #1 stuffing box, five plungers, packing and male and female adapters.

Had pump tested.

M-2 The West CCW heat exchanger essential service water outlet valve, WM0-737, was leaking by.

Replaced the butterfly valve with a new valve and had it tested.

M-3 The West residual heat removal pump motor had an oil leak. Re-placed the top bearing cover gasket and had the pump tested.

M-4 The South safety injection pump had high vibration indication.

Disassembled pump, straightened shaft, shimmed intermediate covers, balanced and lapped impellers and realigned pump to motor. Had the pump tested.

M-5 The power operated relief valve for #3 steam generator, MRV-233, was leaking by.

Replaced the valve internals and had the valve tested.

C&I-l Pressurizer level channels NLP-151 and NLP-152 were in disagree-ment of approximately 5% of level span. Recalibration of the pressurizer level transmitter, NLP-151, was completed with the unit at a power level of 5% or less. This brought the level in-dication channels into close agreement.

C&I-2 Non-essential service water containment isolation valve from #4 containment lower lent, WCR-914, failed closed. The difficulty l

was due to excessive moisture build-up in the "Asco" actuating valve coil. The coil housing was dried and the defective coil was replaced. After repairs, valve closing time was 7.8 seconds.

C&I-3 Feedwater regulating valve, FRV-240, to steam generator #4 would not control properly in " automatic" and would occasionally cycle open and shut without command. Observation of the valve disclosed excessive movement, which was corrected by adjusting the booster i

sensi tivi ty. The positioner, "Asco" valve and piping were examined l

l for leaks; none were found.

I C&I-4 Non-essential service water containment isolation valve from #4 containment upper vent, WCR-932, kept tripping closed and caused a " ground" alarm on "CD" battery. Water had entered the "Asco" valve coil and had shorted it to ground. The "Asco" coil housing l

was dried and the coil was replaced.

Correct operation of WCR-932 was verified by stroking it.

1 L-

.o DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 11-12-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-590T PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER,1982 C&I-5 Heat tracing circuit #411 would not maintain temperature above 1450F on "N" boric acid filter pressure line to QPI-416 and -417.

The problem was diagnosed as a open-circuited heat tape. The defective tape was replaced by maintenance personnel.

C&I-6 Reactor coolant loop 4 delta T/T average protection set IV lost its input signal from upper flux detector N44. To enable testing of the protection set, the associated bistables were placed in the

" trip" mode.

Isolation amplifier NM-307 in N44's electronics drawer was found to be microphonic.

Replacement of this amplifier restored operation to the N44 signal input. The bistables were reset, having been in the trip mode for approximately 26 minutes. No further prob-t lems were encountered with loop 4 delta T/T average.

C&I-7 Pressurizer level instrument loops, NLP-151 and -152, displayed a 5% difference in readings.

The reference leg of NLP-152 was refilled.

No change in level indication was noted.

Recalibration of NLP-152 i

disclosed that this loop had been 2% high.

C&I-8 Non-essential service water containment isolation valve, WCR-914, to #4 containment lower ventilation unit was inoperable due to i

rainwater entering the "Asco" solenoid actuating valve coil. The shorted coil was replaced and the valve was time-tested at six seconds.

C&I-9 Critical control room power circuit #22, which feeds the radiation monitoring system electro-larms, repeatedly tripped its circuit i

breaker on high current flow.

"HFA" relay R-1924 was found to be causing the excessive current drain on circuit #22. The relay was replaced.

C&I-10 Non-essential service water containment isolation valve, WCR-914, feeding #4 containment lower ventilation unit was inoperative due i

to rainwater short-circuiting its "Asco" solenoid valve. The de-fective "Asco" coil was replaced and the WCR was time-tested.

_ _ -

ML20071Q773

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