ML20107L860

Monthly Operating Rept for Sept 1984

ML20107L860
Person / Time
Site:	Cook
Issue date:	09/30/1984
From:	Climer, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8411130675
Download: ML20107L860 (7)

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. DCCTI NO.90-316

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. . - DATI 10/2/84

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. 616-465-5901 C???aT*NG 5 A I*E .

1. Uni: N =.. Donald C. Cook 7 Nor:s . ,

,-. .Re-or" . ,.* #.cc Septanber 1984 -

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3. t '---* d. Th-- ' ?:wer p. W::: 3411 ,

4. N =:rizi:?.:: .;(Cro::5:W:): 1133 .

5. Desi;= II:=:i=! R..:ia;(Nec 51We): 1100

6. 3" " :== De::=>:hte Cay::i:f (Cress 31We): 1100

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2 C:-- d-h!: C===:7 (Nec 31We): 1060 .

S. If C.=;;s C:=:in Capui:7 R::i=;: (1::== Ne=h:: 3 I..:: -h -) SI::: I.=: R: er:. Cive R:==ns: .

9. Power !. ve! To W5d 5- R==i=:e'. !! Any (N:: 5:We): *

10. R : sons .ror R...=-;::i:::.1f A v. : .

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Pis 5 ton:h Yr.-te-C :: . Cu==!::ive

11. Hour: != '.:;o:.!:; P::i=d  ??n 6.579 99.199 12 Nu=h:r Cf Hec = R==::rw:: C i:i=t .

700.8 3,582.4 41,367.6

13. Re:c::r R=sene Sw:d=vm H:= 0 0 0

14. Ec== Ce: _-t:: Ca.I.i. = -

691.1 3,496.8 40,296.9

15. Uni: R- erve Sh :down Ec:== 0 0 0

16. Cr:ss Th==:1 I::::;r Cen==: d (5 WH)  ? '4?9.729 11.489.712 ,129,962,680

17. Ccore. II :=:=12:. .;y Ces=::d t..'.!WE) 745.310_, 3,733,550 41,960,160

13. Net II:=:i=1I ::;y Cce==:::: g,;WH) 719.171 3.603,327 40,456,698

19. U. i

Serri= .:=::r 96.0 53.2 70.9

20. Uni: Astil:hi!!:7 .:=:or 96.0 53.2 70.9

!. Uni: C::::d:/ 7==r(Usin; .ittC Net) -

, 94.2_ 51.7 67.7

22. Unit C.:ceci:y F::::.-(Usin; O Ey, -)<:) 90.8 49.8 66.4 O.3. Uni: . Tor::d Cc:::: R :: 4.0 3.1 13.0]

04. Sh : dawns Sched !:d Cver Ney.: 3.\to..::s (Ty;e. 0:::.:r.d 0 =::en afI::J. I: ,

c:nvvnil l nnco & Maintnnnnce Outace scheduled to st-net 12/22/84. Estinn'ted dur-ation-two weeks.

25. If Sh : Down A: E::d Cf R:;::: ?:-icd. I:::==:ed '::: ei 5::r .:::

25.' Units la Tc:: S::: s Pnorio C:==:=i:10:en:ic..r: Fore _:t Ae .ieved 1.N.I ..- .,. .. e.. .. .. w.s . t .! .f .

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,: p AVERAGE DAILY UNIT POWER LEVEL 00CXET NO. 50-316 UNIT 2 DATE 10/2/84 COMPLETED BY D. Climer TELEPHONE (616) 465-5901 i -

! MONTH nnnenmsor 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(MWE-Net) (MWe-Net) 4 1 1038 17 1030 2 1037 18 1050 .

3 1047 19 1065 .

4 1049 20 1061 5 1049 21 1060 6 1050 1054 22 7 1051 23 los2 8 1053 24 1059 l 9 1055 25 1061 10 1052 25 1064 l 11 609 27 1065 l

l 12 ,a 28 1060 t

13 gr;7 29 1057 14 1o56 30 1065 15 1058 31 l

16 1036 i INSTRUCTIONS On this fonnat list the average daily unit pcwer level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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DOCKET NO. 50-316 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 2 '

DATE October 4 1984 September, 1984 COntPLETED HY B.A. Svensson HEPORT Af0NTil TELEFilONE 616/465-5901

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-, jg 3 E* 1 icensee ,E,*,, "1. Cause & Can secsive No. D.ite Q 5@  % .2 s $ livent p pO Acti.m to H y5 $ j g5 g Repos ** un U g Prevens itecturence 6

149 840911 F 16.1 A 3 84-024-00 EF INSTRU A reactor / turbine trip occurred from 100% power due to a failure of vital A.C. instrument bus, CRID III, invert-er. The inverter failure was due to a failed capacitor, C-2. The inverter was repaired and the Unit returned to service at 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br /> on 840912.

150 840912 F 12.8 G&H 3 84-025-00 ZZ ZZZZZZ At 0733 hours0.00848 days <br />0.204 hours <br />0.00121 weeks <br />2.789065e-4 months <br />, 11 minutes after the Unit was paralleled, a turbine /re-actor trip occurred due to High-High water level in No. 2 steam generator.

The high steam generator water level ~

occurred due to overfeeding the steam generator. This was caused by a com-bination of operator error and level control problems while with feedwater control in manual. The Unit was re-turned to service the same day and 100%_ reactor power was reached on

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840913.

l 2 3 .I 12: 170sced Reason: Me:In>J: Exinbit G -Instsuctions S: Stheiluted A Fipupmer.: I;adme(Explam) 1 Manual for Picparation ut Data li-Maintenance or' Test 2 Manual Scram. linisy Slicens fm I.icensee C Refueling 3 Automatic Steam. livent Iteposi (11RI l'ile iNilRIL D Regulasuiy Resiliclion -l-Othes ( E xplain) 0161) 110perato l'saining & l.icense I:xamination 12 Administeative G Opesalion.il Essos (Explaint Inhibit I - Same Somce r8/77) 11 Othes (Esplain)

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m UNIT SHt TDOWNS AND POWER REDUCTIONS

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INSTRUCTIONS This report should describe all plant shutdowns dunng the in accordance with the tab:a appearing on t'te report form.

report penod. In addition.it should be the source of explan- If category 4 must be used. supply brief comrnents.

i atton of significant dips m average power levels. Each signi. '

ficant reduction in power level (grnter than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable in 'averase daily power lesel for the preceding 24 hnurs) reportacle occurrence pertammg to the outage or power should be noted, even though the umt may not have been reduct:en. Enter the first four parts (event year sequent:a!

shut down completelyl . For such reductions in power level, report number. occurrence code and report type) of the five the dursuon should be listed as zero, the method of reducuan part designation as descnbed in item 17 of Instruct:ons for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-016th This information may not be Cause and Correcuve Action to Prevent Recunence column immediately evident for all such shutdowns, of course, smee 1 should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power 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 pas tive indication of this lack of correlation should be

, bet assigned to each shutdown or signancant reductionin power noted as not applicable (N/A).

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

an entry should be made for both report periods to be sure reduction ortgmated should be noted .oy the two dig 2t code or.

all shutdowns or sigm6 cant power reducuons are reported. Extubit G -Instrucuans for Preparanon of Data Entry Sheets Until a unit has achieved its first power generatien, no num, for Licensee Event Report (LER) File (NUREC.0161).

ber should be assigned to each entry. Systems that do not 6t any existmg code snould be designs.

g ted XX. The code ZZ should be used for those events where DATE. This column sould indicate the date of the start a system is not applicable.

of each shutdown or sigmncant power reduction. Report

as year. menth, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate componen

as 770814 When a shutdown or sigmficant power reducuan from Exhibit ! Instructions for Preparation of Data Entr3

! begins m ene report penod and ends m another, an entry should Sheets for L' ensee Event Report (LER) File (SUREG.0161).

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

or ngmncant power reductions are reported. ,

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

duled." respecuvely, for each shutdown or signifbant power B. If not a component fadure, use the related component.

reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated through error; hst valve as initiated by no later than the weekend following discovery component.

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

ment is required in categonzmg shutdowns in this way. In C. If a chain of fatlures 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. inc!ud.

g 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 Components that do not fit any existing code should be de.

beyond the end or a report penod. count only the time to the signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensumg down time events where a component designation is not applicaole.

1 in the following report penods Report duration of outages

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

' CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

RENCE. Use the column in a narranve fashion to ampitfy or tor was on line should equal the gross hours in the reportmg explam the circumstances of the shutdown or power reduction penod. The column should include the spectile cause for each shut.

wn r ugnu ant pwn reducon ad h unmdate and REASON. Categonze by letter designation in accordance contemoisted long term corteenve action taken, if appropn.

with the table appearmg on the r. port form. If category H ste. This column should also be used for a desenption of the .

i must be used.suppiy brief eumments.

ma or safety.re!sted corrective mamtenance performed dunna the outage or power reduction mcluding an identificanon of METHOD OF SHUTTING DOWN THE REACTOR OR the cntical Path JeuvitY 2nd 2 report of any smale release et REDUCING POWER. Categonze by number designatten radioaetmty or smgle radiation exposure specificaily associ.

1% e that this differs from the Edison Electne Institute ated with the outage wiuch accounts for more than 10 per ent IEEll derimtions of " Forced Parnal Outage" and " Sche. of the allowsoie annual values.

duled Partial Outage." For these terms. eel uses 4 hange or' For long textual recorts contmue narrative on separate pacer

.t0 MW as the break pomt. For larger power reactors.30 MW and referen.e the shutdown or power redustion no tm>

s ti.o > mall 4.hange to war ant esplanation. nJrrative, l

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i Dockat No.: 50-316 Unit Namn D.C. Cook Unit 2 Completed By: G. J. Peak

> Telephone: (616) 465-5901 Date: 10/04/84 Page: 1 of 1 MONTHLY OPERATING ACTIVITIES - SEBTEMBER, 1984 HIGHLIGHTS:

The unit entered the reporting period in Mode 1 with the reactor at 100% of rated thermal power. The unit tripped on 9-17-84 due to the failure of the Crid III inverter. The inverter was repaired and the unit was returned to service.

The unit tripped again during the power accension following the previous trip. The cause of this second trip was Hi-Hi steam generator level. The unit was returned to service again and subsequently loaded to 100% power where it was operating as the reporting period came to an end. No other major power reductions occurred during the reporting period.

Total electrical generation for the month was 745,310 MWH.

SUMMARY

9-04-84 The East Containment Spray Pump was inoperable for a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period due to the pump Delta P being in the the high action range of the ISI pump review program.

9-11-84 The unit tripped at 1517 hours0.0176 days <br />0.421 hours <br />0.00251 weeks <br />5.772185e-4 months <br /> due to the failure of the Crid III inverter.

9-12-84 The reactor was made critical at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> and Mode 1 was entered at 0508 hours0.00588 days <br />0.141 hours <br />8.399471e-4 weeks <br />1.93294e-4 months <br />. The main turbine was rolled at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br /> and the main generator was paralleled at 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br />. The unit tripped at 0733 hours0.00848 days <br />0.204 hours <br />0.00121 weeks <br />2.789065e-4 months <br /> due to Hi-Hi steam generator level. The reactor was taken critical again at 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> and Mode 1 was entered at 1628 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.19454e-4 months <br />. The main turbine was rolled at 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br /> and the main generator was paralleled at 2029 hours0.0235 days <br />0.564 hours <br />0.00335 weeks <br />7.720345e-4 months <br />.

9-13-84 Power reached 100% at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />.

9-15-84 Power was reduced to 97% at 1012 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.85066e-4 months <br /> for turbine valve testing.

9-18-84 Power was returned to 100% at 1138 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.33009e-4 months <br />.

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.

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DOCKET No. 50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 10-5-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTE"ANCE SEFFEMBER, 1984 M-1 Replaced three (3) studs and two (2) standoffs on Unit 2 AB Diesel Generator Exciter diode ring. Torqued all nuts and tack welded. Cleaned exciter and generator windings. Re-connected all wiring and returned unit to service.

C&I-1 2CD-2 Battery Charger lost output voltage while the charger was in service. The C-1 capacitor on the gate filter was replaced on boards 2, 3, 4 and 6. A defective firing board

1. F4 was also replaced. The float and equalizing voltage were adjusted to 260.5 vde and 277 vde respectively. The current limit was adjusted to 110 amps. Declared 2CD-2 Battery Charger operable at 1057, August 29, 1984.

C&I-2 Containment Atmosphere Radiation Monitor, ERS-2400, failed to shift from AC power to battery backup when the normal AC supply, CRID III, failed. The battery backup circuit had failed and was replaced.

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'L moam aDonald arcwaa rucrac cman C. Cook Nuclear Plant P.O. Suu 458, Bridgman, Mchgan 49106 October.j,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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of September, 1984 is submitted.,

Sincerely,

g. -

W. G. Smith, J .

Plant Manager i WGS:ab Attachments

, cc: J. E. Dolan M..P.'Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O.'Bruggee (NSAC)

R. C. Callen' S. J. Micrzwa R. F. Kroeger B. H. Bennett.

J. D. Huebner.

(

J. H.' Hennigan Z. Cordero R. F. Hering J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department 9 ss

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