ML20077H721

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Monthly Operating Rept for June 1983
ML20077H721
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 07/14/1983
From: Gillett W, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8308110242
Download: ML20077H721 (8)


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M C? ERAT:NC DATA REPORT

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5d-315 DCC:

NO.

DATI 7-1-83 CO3t?LE ID gy W.T. Gi I Iett TILI?SCSI _16-465-5901 6

c? int!NG s ATus DONALD C. COOK 1

Not:s

1. Uni:Nac:::

JUNE, 1983

2. Reportis; Pe:iod.:

3250

3. Lkansed Th--! ?ower (MW:1:

1089

4. N2=e !ai: R :i=;(Cross 51We): _

1054 S. Desig: E!e_ ':=1 R::ia;(Nec 51We):

1080

6. y "-=== Dependste Cap =i:7 (Gross 51We):

1030 T. Si=F m De; d-% C:p::i:7 (Nec MWe):

E. If Ch::; s C:=:in C:p=i:/ R::!=;:(1:t:-s Number 3 Thret;h D Sine: Lan Repert. Give Reasons:

ITEM 7 CHANGED FROM 1044 TO 1030 AS OF JUNE 1.1983 DUE CHANGING THE CONTROL VALVES T0-FULL ARE ADMISSION. THIS ALSO CHANGES ITEM 21.

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9. Power Leve! To Whi=h R=r=i=-d,!f Any (N:: MWe):
10. R== sons For R:-Joss.If A=y:

This Month Y.-co-Datz Cu==htive 720 4,343 74.471

11. Hours != Repor.ing ?=iod 720 4,257.3 56,138.9
12. Nu=b=r of Hoes R== r W:s Cri:i=1 0

0 463

13. Rc==r Rese:ve Sh::down H:=s 720-4,250.6 54.963.5
14. Ho=s Ce===::: ca.L:n 0

0 321

15. Uni: Reserve Sh:tdown He=

2,182,703 13,298,419 160.600.979

16. Cross The==:! I::::y Cen:=:ed OtWM)
17. Cross Se==i=1Ine;7 Ce:

-d G.lW H) 713.270 4.367.780 57.R03.630

13. Net E==:i=1I:=;y Ce===::d C.:Wc-)

687,136 4.213.147 50.806.648

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100 97.9 76.0

19. Unit Serri= F:c:ce 100-97.9 76.0
20. Uni Av:ilshiII:r.::::or N.7 93.1 68.9
21. Unit C:pci:y E==:r(Usi=; MDC Net)
22. Unit Caescity. :=er(Usin; DIR.4et) 90.5 92.r=

65.9 0

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R.0

23. Uni:.:or::d Cu=ge Race
24. Sh:: downs scheduled over Nex: 6 Mor.:bs (Type. D:te.: d De= ion or I:6i:

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UNIT 1 REFUELING 7-15 to 9-11-83

~5. If Sh:: Dowrt Ac Isd Of Report ?=iod. Esti==:ed D:te oistar::p:

.25' Units la Tes: S::::s (? for to Ce===::!s! Open: font:

Foreest Adieved INIT:AL CRIT *CALITY IN:TIAL I'.ICTR:CIU i

COM.*.:IRC:A:. 0? ERAT;ON l

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?O}YI AVERAGE DATLY UN1T POWER LEVEL DOCKET NO.

50-315 UNIT 1

i DATE 7-6-83 COMPLETED BY Ann Might TELEPHONE (616)465-5901-MONTH JUNE, 1983 DAY eAVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1028 17 1018 2

1028 18 981 3

963 19 981 4

529 20 980 5

518 21 982 6

869

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22 981 7

1028 23 980 8

1018 24 976 9

1027

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25 944 10 1021 25 939 11 1025 27 931 12 1026 28 925 13 1025 29 925 14 1023 30 925 15 1012 31 16 1021 I

INSTRUCTIONS On this fomat list the average daily unit power level in MWe-Net for each day in the reporting month. Ccmoute to the nearest whola mecawatt.

50-315 DOCKET NO.

UNITSiluTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 1 DATE 7-14-83 REPORT MONTil JUNE, 1983 COMPLETED HY B.A. Svensson TELEPilONE 616/465-5901 SHEET 1 of 1 "t.

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202 830603 F

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CH PIPEXX Reactor power reduced to 55% to re-move the West main feed pump from service to repair weld leak on a 1" drain line connection on the pump discharge piping. Reactor power was maintained at 55% over weekend due to low system demand and was returned to 100% on 830606.

A slow power reduction to 90% was started on 830624 to extend core life.

90% reactor power was reached on 830627.

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F: Fo ced Reason:

Method:

Exhibit G -Instrucihms S: Scheduled A l?quipmens Failme(Explain) 1-Manual for Prepasation of Data li Maintenance of Test 2 Manual Scram.

Entry Sheets foe 1.icensee C Refueling 3-Automatic Scram.

Evens Repose (i.ER) File INURIL D-Regidaimy Rest:iction Othes (Explain) 01611 E-Ope:ator Training & License lixamination F Adminisisalive 5

G Operational Estor (Explain) lixhibit 1 Same Somcc l'l/77)

Il Other (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the

n accordance with the table appeari: g on the report form.

report period. In addition. it should be the source of explan-If category 4 must be used, supply brief comments.

ation of significant dips in average pow <r levels. Each sieni.

ficant reduction in power level (greater than 20"e 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 />) reportable occurrence pertammg to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequenttal shut down completely. For'such reductions in power level, report number, occurrence code and report type) of the five l

the duration should be listed as tero, the method of reduction part designation as described in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-01611 This information may not be Cause and Correenve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully tunhet investigation may be required to ascertain 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 positive indication of this lack of correlation should be ber assigned to each shutdown or signtilcant reduction in power noted as not applicable (N/A).

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

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

an entry should be made for both report penods to be sure Exhibit,.v Instructions for Preparation of Data Entry Sheets all shutdowns or sigmficant power reductions are reported.

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 existmg 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 applicable.

of each shutdown or significant power reduction. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814 When a shutdown or significant power reuuction from Exhibit ! Instructions for Preparation of Data Entr) beg:as in one report penod and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0161).

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

or sigmficant power reductions are reported.

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

If not a component failure, use the related component:

reducuon. Forced stutdowns include those required to be e.g.. wrong valve operated through error: list 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 categorizmg 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 described action was taken.

under the Cause and Corrective Action to Prevent Recut-rence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any existmg code should be de-beyond the end at 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 ensuing down time events where a component designation is not applicable.

in the following report periods. Report duration of outages rounded 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 hours the genera.

RENCE. Use the column in a narrative fashion to amplify or for was on line should equal the gross hours m the reportmg explain the circumstances of the shutdown orpower reduction.

penod.

The column should include the spec!fic cause for each shut-i down or significant power reduction and the immediate and REASON. Categonze by letter designation in accordance eith the table appearing on the report form. If category H centemplated long term corrective action taken. if appropri-ste. This column should also be used for a de:enption of the must be used. supply briet comments, major safety-related corrective maintenance performed dunng METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction includi: g an identification of REDUCING POWER.

Categonze by number designation the entreal path aettvity and a report of any sinele release et radioactivity or smgle radiation exposure speettically associ-INote that this differs from the Edison Electric Institute sted with the outage which accounts for more than 10 percent IEE!) detinitions of " Forced Pantal Outaae" and " Sche, of the allowable annual values.

duled Panial Outage." For these tenus. eel uses a change of For long textual reports continue narrative on separate paper I

.t0 MW as the break pomt. For larcer power reactors. 30 MW and reference the shutdown or power reduction foi this

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is t.io small a change to warrant explanation.

narrative.

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' Docket No.: 50-315

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Unit Ntre:

D. C. Cock Unit 1 Completed By:

C. E. Murphy i

Telephone:

(616) 465-5901 Date: July 6, 1983 Page:

1 of 2 I

MONTHLY OPERATING ACTIVITIES - JUNE 1983 l

Highlights:

The Unit operated at 100% power until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on June 17, at which time pcwer was reduced to 95% to extend core life.

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On June 27, power was further reduced to 90% and has j

remained at 90% for the remainder of this reporting period.

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Also during this period a load drop to 55% for repair to the West Main Feed Pump and 2 load drops to 95% for Turbine a

Valve Testing were made. These are addressed in the summary, i

The gross electrical generation for the month was 713,270 MWH.

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Summary:

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06/01/83 The West Component Cooling Water Heat Exchanger j

was out of service for a 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> period to remove j

and calibrate a safety valve on the Essential Service Water Supply to' the Heat Exchanger.

The Containment Hydrogen Sampling System was removed from service for a 2.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period due -

i-to repairs to the sampling pumps.

06/03/83 Reducing power to 55% at 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br /> to repair a.

j leak on the discharge line-of the' West Main

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Feedwater pump. Returned to' 100% at 1314 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.99977e-4 months <br /> on 06/06/83.

1 06/10/83 Reducing power to 95% at 2130 for turbine valve testing. Returned to 100% at 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> on 06/11/83.

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06/13/83 The Unit Vent Radio Gas Monitor (R-26) was inoperable for a 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period to. replace 4

power supply.

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06/17/83 Reducing power.to 95% at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> for turbine.

l valve testing. Power remained at 95% to extend L

' core life.

l 06/22/83 The High Demand. Fire pump-was' inoperable for:a.6 l

l hour period to wire in ZPS-11.

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D ckst No.: 50-315 Unit NIme:

D. C. Cock Unit 1 Completed By:

C. E. Murphy Telephone:

(616) 465-5901 Date: July 6, 1983 Page:

2 of 2 Summary:

(continued) 06/23/83 1-HV-AES-1 (Aux. Building Supply Fan) was inoperable for _ a 11.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period to change the rollomatic filter.

The East CCW pump was inoperable for a 6.5. hour period to change oil in the hearings.

06/24/83 The West CCW pump was inoperable for a 4.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period to change oil in the bearing.

The 1-HV-AES-2 (Aux. Building Supply Fan) was inoperable for a 9.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period to change the rollomatic filter.

At 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> a slow power reduction to 90% was started to further extend core life. At 90%

on 06/27/83.

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 04/05/E3. The backup CO system remains 2

operable.

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DOCKET No.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 7-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1983 M-1 A leak was identified on a capped leakoff line on pressurizer spray control valve, NRV-163. The valve packing was adjusted and the leak-off line was replaced.

C&I-l While testing the power / load unbalance system in the turbine gen-

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erator electrohydraulic control cabinet, a turbine runback occurred.

l A Rosemount pressure transducer for cold reheat pressure had failed high. The transmitter was repaired and reinstalled.

C&I-2 Pressurizer level indicator, NPL-153, on pressurizer level protection set III deviated 7% from other level indication channels. The chan-nel was declared inoperable and its associated bistables were placed in the " trip" mode. Level transmitter NPL-153, reference leg, was pumped full of water to restore that channel to operability. Channel deviation was then less than 1.5% of level span.

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~~",, INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NULLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 July 14, 1983 Director, Office Of Management Information and Program Control

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U. S. Nuclear Regulatory Commission

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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 June, 1983 is submitted.

Sincerely, u

W. G. Smith, Jri.

Plant Manager WGS:ab Attachments cc:

R. S. Hunter J. E. Dolan M. P. Alexich R. W. Jurgensen 4

NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center ZG2y IlI