ML20207C358

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Monthly Operating Rept for Apr 1986
ML20207C358
Person / Time
Site: Cook 
Issue date: 04/30/1986
From: Bruck D, Czajka, Svensson B
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8607210349
Download: ML20207C358 (6)


Text

t' N.R.C.

OPERATING DATA REPORT DOCf.E F NO.

50-316 DATF 05/02/86 COMPLETED BY CZA. TEA TELCf-1 TONE 616--465-5901 OPERATING STATUS 1.

Unit Name D.

C.

Cook Unit 2 2.

Reporting Feriod AFRIL 1986 l notes 3.

Licensed Thermal Power (MWL) 3411 l 4.

Name Plate Rating (Gross MWe) 1133 l 5.

Design Electr I cal Rating (Net MWe) 1100 ;

i 6.

Maximum Dependable Capactty (GBOSS MWe) 1100 l

7 Maximum Dependable Capacity (Net MWe) 1060

- - - - - - - - - - - - - - ~ - - - - - -

S.

If Ch a n g es-Occur in Canacity Ratings (Items no.

I through 7) Since Last Report Gi m R o a = o n e _ _._ _ _.._ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._.

9.

F 'ower Level To Wh t 1.h Feutricted. If Any (Not MWe) _____,_____________

10. Reasons For R".+trictionr.

If A n y : _ _ _ _ _ __ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ ___ _______ _ _ _

_ ~ _ _ _ _. _. _.. _. _ _ _ _ -..

This Mo.

Yr. to Date Cumm.

Il Hou r <- in Reporttog Period 719.O 2879.O 73007.O I?

No. o4 Hre Reactor We Cr i t i <.a l O.O 1352,6 50381.4 17 N actc< Re=erve S h u f.d a w n H::iu r s O.O O.O O.O 14 Hni n Generatar en

1. 3 ne O.O 1272.5 49126.1 in r;ni t F-or o % r rfi o ni Hn.n -

.O O.0 0.0 1<

Gr,== ! t er m.

F:mr o

-.m Msn t,

O T404597 154675207 L7 O e +.- El ec. t Fne. j. Ge,

( N !!i O

1097730 50784370 la 66: El m t

-: men, n.

'MWH>

0 10534~72 48954840 19.

j n i t-cce

.co F c,

' ac O.0 44.2 69.6 N

l ' r. t A..ii} e2)it Fscter 0.0 44.2 69.6 lle 1 L Ciw es R

'or (MDC Net) 0.0 34.5 65.5 7,

t ir.1

  • iscior GEP ? !e t )

O.O 33.3 64.**

etc>- '

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Un o r

~r. N Ou v..o.

Th. t o 0.0 99 15 7

ti. Oh!It d ot 'o n '~ ~ h e d t i e d ovEr Ne:: L 51: Menths (Type Date and Duration):

f ht Down At End of Rooort F er i od. Estimated Dm.e of Startup:

FH 'T nnWN FOR REFUELIN:

FCT: MWiED OTTsP fi 'P

.lUNF 1,1936

^H.

IF. t in Test Status W,

i <,r to > mmm etal Operation):

Forca,t Achieved INITIAL CRITIC 9LliY IN! 0 7 n1 - E r r7 R ir:1Ty

(~ f J o i y

'Cs ih.,1 Tijr'-

[ F.J 4 8607210349 860430 PDR ADOCK 05000316 lh R

PDR

4 AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 05/02/86 COMPLETED BY CZAJKA TELEPHONE 616-465-5901 MONTH APRIL 1986 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 4

1 1

0 17 0

3 2

0 18 O

J 3

0 19 O

l 4

0 20 0

j 5

0 21 0

6 0

22 O

i 7

0 23 0

8 0

24 0

9 0

25 0

j 10 0

26 0

11 0

27 0

12 0

28 0

t' O

29 0

t4 0

50 0

l5 v

41 O

16 O

l 1

i m.,

50-316 4

I ilNit' SilillllOWNS ANil PIHVI:lt Hl:llilrilONS IHM'KEI NO[D.C. Cook, Unit 2 i

tlNII' N AMI:

l IIA IE 5-6-86 B.A. Svensson COkiPI E1Eli tiY A ril, 1986 P

'IEl.l:PilONE 616/465-5901 HI POHI Alf) Nill l

1 4

i "t.

w

=

p i iccusee

[j-e,,

b, rense a roi ctiive yE

'y j s'j 8

Atinnien No.

Dale R

js' y n

.c s c2 livem y,'d pU

[$

Hepor #

iA O Psevens Itecierscue c b

6 172 860228' S

720 B&C 1

N.A.

ZZ ZZZZZZ The Unit was removed from service on 860228 for Cycle 5-6 Refueling Out-age.

The core has been unloaded and the control rod guide tube split pin replacement and the steam gen-erator eddy current testing and tube plugging completed. The estimated return to service date is June 1,

1986, i

i l

i i

3 3

4 1:: 1 oneti iteason; hicehnil:

1:alnlist G Insesucti.ms S: Silicilulcil A lingnipmens I ailme (l.nplain)

I hiannal lui l'sepaiainm ni paia 11 hiainienance ns Test 2 Manual Scsam.

linisy Slicess l'ne Iicensee C Hefueling

.l Ananmatec Sisam.

I: vent Itcimes il l'Iti l'ile (NiiHI G.

1) Hegislatoiy Hestsiction 4 Othes Ilinplamn tiltil) 1 Opesaios l'eaining A Ikcuse I saminailun 5

I: Ailnunisisasive ITintine 1 Same Soun e G Ogreatismal 1:eno llinplaint l's/1/l 11 Ollice Ilimplain t

t Docket No.:

50-316 Unit Name:

D.C. Cook Unit 2 Completed By:

D.

A.

Bruck Telephone:

(616) 465-5901 Date:

May 7, 1986 Page:

1 of 1 MONTHLY OPERATING ACTIVITIES - APRIL, 1986 HIGHLIGHTS:

The reporting period began with the reactor coolant system in Mode 6 at 105'F.

All fuel was removed from the reactor vessel.

An Unusual Event was declared when both diesels were taken out of service at the same time.

This was a planned event.

The reporting period ended with all fuel removed from the vessel and the reactor coolant temperature at 85 F.

SUMMARY

04-01-86 At 0128, the reactor cavity floodup was stopped due to excessive reactor cavity seal leakage.

At 0654, with the reactor cavity drained down the reactor vessel head was reset on the vessel to repair leaks on the reactor vessel nozzle cover seals.

At 2155, the CD diesel generator was manually tripped due to failure of the No. 4 main bearing.

04-04-86 At 1115, the reactor vessel head was removed and at 1128 the reactor cavity floodup was started.

04-05-86 At 0115, fuel movement to unload was started.

04-07-86 At 1216, all fuel was removed from the reactor vessel.

04-08-86 At 0802, the AB diesel generator was removed from service for the 18-month surveillance inspections.

This left the Unit with both diesel generators inoperable, placing the Unit in an Emergency Plan

" Unusual Event" condition.

This procedure was reviewed and notifications made to the appropriate regulatory bodies prior to the event.

1

~

04-29-86 At 0229, while performing a surveillance test, a wire j

was shorted in nuclear instrument power range drawer N-41, causing reactor trip signals.

1 I

- -- - ~..

4 I

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 l

DATE 5-8-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 i

PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE i

APRIL, 1986 M-1 CM0-413, Component Cooling Water west suction crosstie will not 1

close. Freed up sticking torque limit switch. Valve tested i

l satisfactorily.

t l

C&I-l The ASCO solenoid valves that control supply air to nonessential service water containment isolation valves WCR-953, WCR-957 and

'[

WCR-946 are stuck, supplying air to the NESW valves and venting off at the same time.

i The ASCO solenoid valves were re-built and correct operation of l

each of the NESW valves verified.

l I

C&I-2 N-32, Source Range indication is reading erratically. Found de-l tector canister full of water. Dried out canister, replaced in-l sulators, re-installed cables, re-installed detector in well and performed surveillance test to declare N-32 source range channel operable.

C&I-3 IRV-310, east residual heat removal heat exchanger outlet regu-lating valve has an air leak on valve controller.

I A pilot valve was found leaking.

Repaired pilot valve, calibrated i

valve positioner and verified proper valve operation.

i l

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l 1

l 4

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3-h L{hbb i

x maan acuma nicmc_comn Donald C. Cook Nuclear Plant P.O. Box 458 Brdgman, Mchgan 49106 May 8, 1986 I

l Director, Office Of Management Information l

and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

A 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 April, 1986 is submitted.

Sincerely, 3

J W.G. Smith,Jr&

L /

N i

4 Plant Manager 1

4 j

WGS:ab

'1 Attachments j

cc:

J. E. Dolan M. P. Alexich 3

R. W. Jurgensen j

NRC Region III B. L. Jorgensen l

R. O. Bruggee 4

i R. C. Callen S. J. Mierzwa i

F. S. VanPelt, Jr.

P. D. Rennix l

D. R. Hahn Z.

Cordero j

J. J. Markowsky J. F. Stietzel a

PNSRC File j

INPO Records Center

^

ANI Nuclear Engineering Department 1

i o

dr l

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