ML20128B094

Monthly Operating Rept for Apr 1985

ML20128B094
Person / Time
Site:	Cook
Issue date:	04/30/1985
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8505240405
Download: ML20128B094 (8)

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N.R.C. OPERATING DATA REPORT l DOCKET NO. 50-315 i DATE 5/1/95 i COMPLETED BY CLIMER TELEPHONE 616-465-5901 >

OPERATING STATUS 4 1.. Unit Name D. C. Cook Unit 1 -----------------------

2.. Reporting Period Apr. 85 notes  :

3. Licensed ThermalePower (MWt) 3250 1

0. Name Plate Rating (Gross MWe) 1152 1 i

5. Design Electrical Rating (Net MWe) 1030 :  : I

6. Maximum Dependable Capacity _(GROSS MWe) 1056 I I -

7. Maximum Dependable Capacity (Net MWe) 1020 --------- - =~--------

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O. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since (,

Last Report Give Reasons _______________________________________ _

_ __________________ _==________=- _-__. - _ _ _ _

=_________

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9. Power Level To Which Restricted. =If Any (Net MWe) _________________ 6

10. Reasons For Restrictions. If Any:____________________ _ _ ___ __

- _ _____________________- __________________- =_______

This Mo. Yr. to Date Cumm.

11. Hours in Reporting Period 719.0 2879.0 90551'.D

12. No. of Hrs. Reactor Was Critical 122.4 1868.0 67561.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0 14.-Hours Generator on Line 122.4 1856.2 66217.7

15. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Gen. (MWH) 341767 5410521 195200094

17. Gross Elect. Energy Gen. (MWH) 112030 1761840 63533730

18. Net Elect. Energy Gen. (MWH) 107515 1694853 61125948

19. Unit Service Factor 17.0 64.5 74.9

20. Unit Availability-Factor 17.0 64.5 74.9

21. Unit Capacity Factor (MDC Net) 14.7 57.7 67.8

22. Unit Capacity Factor (DER Net) 14.5 57.2 65.2

23. Unit Forced Outage Rate 0.0 0.0 7.2

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

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25. ii Shut Down 3EIEn5~~oI~ rep ~ ort PbEi~od~~EStI~m$ted ~ ~D3te oI~5tArtu E912 slid 9_29tas9_9 s tima.t99_ s tart-ue_b?3?st_Lk.198 s_.____ ___ ____pI~ ___

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

Forcast Achieved IN[ITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL CPERATION 8505240405 B50430 PDR ADOCK 05000315 R PDR 1M VI

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AVERAGE DAILY POWER LEVEL (MWe-Net) f DOCKET NO. 50-315

. UNIT ONE DATE 5/1/85 ..

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COMPLETED BY CLIMER j t TELEPHONE -616-465-5901  ;-

b MONTH. Apr. 85 $

AVERAGE DAILY' AVERAGE DAILY 4 DAY- POWER LEVEL DAY POWER LEVEL  !'

i 1 929 17 O t'

2 924 18 J-O g 3 -930 19 0 ,

4 826' O' 20 5 - 839 21 Oi

~6 32 22 O?' ,

7 0 23- O , . . ,.

-B O 24' O q, f/ y ,g; 9 O 25 _O J r?v

10. O 26 0; {g . -

11- 0 27 0- in 12 0 28 0

.13 O. 29 0

.14 0 30 0 15~ O 31 0-

.16 0 4

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t DOCKET NO.

50-315 . .

ilNITSiltiTIM)WNS AND POWER HEIDUCTIONS D.C. Cook, Unit 1 UNIT NAME DATE 5-8-85 COMPLETEllley B.A. Svensson HEPORT MON ~nt April, 1985 . ~ TELEPHONE 616/465-5901 "t. -

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)sgh* liensee ,iig h. Cause & Causective Actiim no No. Dane g-,

5 livent 3,7 g3 I- yE $ ~ ;y, g Hepius e so O g' Psevens Hecisnence 6

246 850406 S 596.6 B&C 2 N.A. ZZ ZZZZZZ The Unit was removed from service at 0221 hours0.00256 days <br />0.0614 hours <br />3.654101e-4 weeks <br />8.40905e-5 months <br /> on 850406 for the ten-year Inservice Inspection and Cycle IX Re-fueling Outage. In addition to the refueling work, major maintenance work includes steam generator eddy current testing, control rod guide tube replacement, main turbine con-denser retubing, replacement of feed pump turbine condensers and Appendix "R" design changes, u

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. 12: FinccJ Heason- Meiland: Exlubit G . Insinactinuis S: Stheiluleil A-linguipinent Failme(Explain) 1-Manual for Psepasasiim of Data ll-Maintenance of Test 2 Manual Scsam- lintsy Sheets fus IAcusee C Refueling 3 Automasse Stam. livens Repose (i.l?R)1 ile INilRI:G-

' Il Regulatoiy Restsicliam Othes (lixplain) 01611 1 Opesatos Tsaining& licenw 1:xaminalism 12 Ailministsalive 5 G Ogmaliunal linin Blixplaml Exinbis I- Same Somce 19/D) II Othe (lixplain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should descnbe all plant shutdowns dunng the in accordance with the taole appearms on the report form, report penod. In adcitron. it should be the tource of explan. If category 4 must be used. supply brief comments.

anon of sigruncant dips m 2verage powerlents. Each signi.

ticant reduction in power lew! (greater than 20", reduction LICENSEE EVENT REPORT :r. Reference the applicable in average daily power !avel for the preceding 24 hnurs) reportsole 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. sequennal shut down completelyl . For such reductions in power level. report number, occurrence ecde and report type) of the tive the dursuon should be listed as zero, the method of reduction part designation as descnbed in item I7 of Instrucuons for should be listed as 4 (Other). 2nd the Cause and Correcuw Preparanon of Data Entry Sheets for Licensee Event Report Action to P. event Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause 2nd Correcuve Acuan to Prevent Recurrence column immediately evident for all such shutdowns,of ceurse, since should be used to provide any needed explanation to fully further invesugation may be required to ascertam whether er desenbe the circumstances of the outage or power reduction. not a reportable occurrence was involved.) If the cutage or power reduction will not result in a reportable occurrence.

. NUMBER. This column should indicate the sequential num. the positive indication of th:s !sek of correlation should be ber assigned to each shutdown orsignidesnt reducuanin power noted as not applicable (N/A).

for that calendar year. When a shutdown or signtricant power SYSTEM CODE. The system in whica the outsge or power reduction begins in one report period and ends n another. ggg an entry shot.ld be made for both report periods to be sure

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sit snutdowns or signulcant power reducuons are reported. Exhibit G . Instrucuons for Preparstiert ot Data Entry Sheets Unt:1 a unit has achieved its f!:st power generation, no num. fM bcusu Ennt Repen DER) Ne MREM 16t h ber should be asugned to each entry. Systems that do not tit any existing code should se deugns.

ted XX. The code ZZ should be used for those events where DATE. This column should ind:cste the date of the start a system is not aoplicaole.

of each shutdown or ugniacant power reducuen. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate .omponent as 770814 When a shutdown or ngrudesnt power reduccon from Exh* t I . Instrucuens for Preparanon of Data Entry begmsin one report pened and ends in 2nother, an entry should Sheets for Licensee Ennt Report (LER) File (NCREG4161).

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

or cgnidcant power reductions are reported.

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

duled.*' respectively, for each shutcown or signiacant power B. If not a component failure, us'e the related component:

reducuon. Forced shutdowns incluce those required to be e.g.. wrong valve operated through errett list valve as innisted by no later than the weekend following ciscovery component.

of an off4tormal condition. It is recognized that somejudg.

ment is requsted in categorizmg shutdowns in this way. In C. If a chain of fadures occurs, the tirst component to mai.

generst 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, saould be desenbed action was taken. under the Cause and Correcuve Acuon to Prevent Recur.

rence column.

DURATION. Self-explanatory. Wher. a shutdown extends Components that do not tit any ex: sung code should be de.

beyond the end or a report penod. count only tne time to the signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensumg down ume in the following report cenods. Report duratson of outaps events where a component deugnation is not toplicscle.

ruunced to the nearest tenth of an hour to fac:litate sommation.

The sum of the total outage hours ptus the hours the pners. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

RENCE. Use the column in a narrative fash:on to amatify or tot was on line should equal tne gross hours in the reportmg explam the circumstances of the sautdown or power reducuen.

penod.

The column should include the specide cause for each shut.

REASON. Categonze by fetter deugnanon in accordance-

• n M Nm csm pown redwumt and the imnwdiau snd with the taole appearmg on the report form. If category H eentemplated long term correcuve scuan taken. if appropn.

must be used, sacciy bnef comments, ste. T'us r column snould also be used for a descrtation of the maior safety.related corrective mamtenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction includmg an idenufication ot}

REDUC:NG POWER. Categonze ov numner dengnanon tne enuest path acuwty and a repon at any ange niesse et radioacunty or smgfe tsdistion exoosure spectiesdy asscet.

INote that this dairers : rem the Edium Eleutne Insutute sted with the outage which accounts for more than 10 :ereen t eel) denmuens of " Forced Par'ts! Outate" and "Sene, of the silowsole annual values.

suled Psctra! Outage." For these temu. eel uses 4 hange at For long textual reports eontmue narrative on separate ;' aper 20 MW as the bress pnmt. For larger puwer rencors. 30 MW .nd referense the shutdown or power re:su uun im tma a sm > mall J .hange to wanant espianatwn. narrative.

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. Docket'No.: 50-315 ~

Unit Ntms: D.C. Cook Unit 1 Completed By: A. S. Puplis Telephone: (616) 465-5901 Date: May 10, 1985 Page: 1 of'2 MONTHLY OPERATING ACTIVITIES - APRIL, 1985 HIGHLIGHTS:

The_ reporting period began with the Unit in Mode 1 at 90% power

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in coast down toward an April 5, 1985 shutdown to begin the Ten

- . Year Inservice Inspection and Cycle 9 Refueling Outage. The' Unit was removed from service at 0221 on April 6. At the end of the reporting period the reactor vessel closure head was removed and the refueling cavity was being filled to the refueling-level.

Gross electrical generation for the reporting period was 112,030 MWH.

Summary:

4-03-85 At 0135, a slow power reduction to 85%-was initiated as part of the coast down. Power reached 85% at 1600.

4-05-85 -At 2055, the Unit shutdown was started.

~4-06-85 At 0221, the Unit was manually tripped from 22%.

At 0640, the 0400 dose; equivalent iodine sample indicated an iodine spike of 4.48 pCi/ml, which is greater than the Technical Specification limit of 1.0 pCi/ml.

4-09-85 At 0724, and again at 0736, an ESF actuation occurred which-caused the containment. ventilation system'.to isolate due to an instrument spike on' containment atmosphere radiation monitor ERS 1301.

At 1214, an ESF Actuation occurred due to an instrument spike on containment atmosphere radiation monitor ERS 1401.

4-11-85 At:0110, an ESF Actuation was caused by ERS 1301.

i At 0615, the Turbine Driven Auxiliary Feedwater Pump l was declared inoperable because it could.not develop sufficient discharge pressure. ,

At 2230, an RCS Cooldown to 500*F was initiated.

4-12-85 At'll15, the RCS entered Mode 4, Hot Shutdown.

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a F 50-315 D ckst No.:

Unit Names D.C. Cook Unit 1 Completed By: A. S. Puplis.

Telephone: (616) 465-5901 Date: May 10, 1985 Page: 2 of 2

, 4-13-85 At 1020, Mode 5 Cold Shutdown'was entered.

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4-18-85 ~At 0210, draining of the reactor coolant system to half loop was started.

4-19-85 At 0955, the RCS was at. half loop.

4-23-85 At 1827, the RCS entered Mode 6, Refueling.

27-85 .At 1021, an Unusual Event was declared per EPP.010, Toxic Gas Release Guideline. The toxic gas resulted from a hydrazine leak on FFC-241 main feed flow controller. The Unusual Event was terminated at 1118.

4-29-85 At 0611, an'ESF actuation occurred due to a spike _an ESF 1401.

At 1015, an Unusual Event was declared as the result of a serious. personnel injury. The Unusual Event was terminated at 1328.

.The Control Room Cable Vault Halon System remains inoperable as of 1400 on 4-05-83. The backup CO System for the Control Room 2

Cable Vault remains operable.

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DOCKET NO. J50 - 315 UNIT NAME' D. C.-Cook - Unit No. 1 DATE 5-8-85 4 COMPLETED BY B. A. Svensson

MAJOR SAFETY-RELATED MAINTENANCE APRIL', 1985

-M-1 During the performance of hydrostatic testing, a seal plate packing spring on the inboard auxiliary stuffing box of the' North Safety Injection Pump failed, Conversations.with the.

', pump manufacturer revealed that-the spring served as a spacer and lacking a replacement could be replaced with a gasket of

. . suitable dimension. Along with the spacer gasket, a new

. mechanical seal was installed and operability; testing was performed 1to ensure the effectiveness of the repairs.

C&I-1 'The."W" Motor Driven Auxiliary Feedpump~ tripped following an automatic start. Two of the.three pressure. switches on'the  ;

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pumps' suction were out of calibration,' tripping at_a higher j pressure than normal. They were recalibrated.. The other.

y switch was found : inoperable, because ent insulator strip' in-

, s terfered with the trip mechanism.. The strip was cut off to prevent the interference, and the; pressure switch was recal-' ,

ibrated.-

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fg=::"._ INDIANA & MICMSAN ELECTRIC C_0MPAN1 Gy,a--

Donald C. Cook Nuclear Plant P.O. Box 458, Bridgman, Mchigan 49106 Blf May 8, 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 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of April, 1985 is submitted.

Sincerely,

~ (1 y)./  ; y W. G. h, 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 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

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