Text

Monthly Operating Rept for Jan 1984
	ML20080T751
Person / Time
Site:	Cook
Issue date:	01/31/1984
From:	Gillet W, Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8403020044
	Download: ML20080T751 (11)
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CPER.C?C DATA R ? ORT 50-315 D CC.~..m.O.

u 2-2-04 Da.-s-

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W.T.Gillett T.~.? T t:_.. C.N: 616-465-5901 O?IhTING S ATUS Donald C. Cook l

Nor:s

- 1. Uru.: h. acte:

January 1994

2. Repor:in; ?::fod:

3250

3. I.I== sed Th --? ?ower (51Wt):

1152

4. N==er!st's ?.::i.;(Cro:s 51We):

1030

' S. Desi;= Ile==i=1 R::in;(Nec 31We):

1056

6. 3f-" ::= Dependshte C:p::i:f (Cross 31We):

1020

7. Siaxi==:n Dep::d:ble

.--3 (Nec 31weyi e

8. If Ch:=;es 0:=rin C:p=i:7 ::i:;s (1::=s Numb :3 F :ou;h 7) Sic:: L:::Repor:. Give R::sens:

R

9. Power Leve! To Which R===i==d. If Any (N:: SIWE):

10. R== sons For R.

foss.If Asy

4 This Stor.th Yr.4o.Ca :

Cu==I::ive 744 744 79,632

11. Hours != R:ponia; ?::fod 12 Nu=her Cf Hoc:s R==:r Was Cri:i=1 567.1 567.1 9A.1R9 1

13. Rc=:r Rese.:ve Sh=:down H::::

0 0

463

- 14. Ho::: Gene =:::Os.Lise 559.9 559.9' '

56,903.6 0

0 321 l

15. U !: R: serve Sh:tdown Ec==

1,743,010 1,743,010 166,087,066

16. Cross The==:1 E..::;y Cen:=::d (31WH)

17. CrossIIe==:=II:::;7 Gen:=::d G.!WH) 575.230 575.230 54,501.520'

13. Net E!::=i=lI ::;y Cer.en::d C.;Wc!)

554,473 554,473 52,434,813 i.

75.3 75.3-73.3 f

i

19. Unit Se:Ti=.::=or 75.3 75.3 73.3

'.C. Uni: Ar..il:hiII.y. :::or.

73.0 73.0 66.3

21. Uni: C: sci:y N:::cr (Usin; MrC Net) 72.3 72.3 63.4

22. Unit C.nescity. :::ce (Usin DER.9et) 24.7 24.7-8.0

23. Uni:.ror::d Cu::ge R:t=

j

24. Sh='dowr.s Schedu!:d Over Ne.u 5.\\ ton:hs (Type. 2::e.:r.d De=:fon af I:r.h1:

i

25. If Sh : Down A: End Of Repert ?:-fed. Esti==:ed :hte c(Sts =p:

5. Units la Tes: 5:::.5 I?nor ta C:====i:1 Ope =:ier.1:

Fore =st Achieved INIT:AL CRIT *CA!JTY

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C O... :..,....,,., A....

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AVERAGE DAILY UNIT POWER LEVEL J

~

DOCKET NO. _ 50-315 UNIT 1

OATE

'2-2-84 COMPL:TED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH January 1984 DAY

-AVERAGE DAIL/ POWER LEVEL DAY (MWE-Net)

AVERAGE DAILY POWER LEVEL (MWe-Net) 1 1029 17 in?9 2

-1027 18 1025 3

1028' 19 1026 4

1029 20 1027 5.

1028 21 1023 6

924 22 1024 7

710 23 588 8

1028 24 9

1029 25 10 1030 25 11 1029 27 12 1026 23 13 1024 29 14 1019 30 1

15 1026 t-31 340 16-1027 I

INSTRUCTIONS On this femat list the average daily unit pcwer level in MWe-Net for each i

day in the reporting month....

Ccmoute. to the nearast whnla ma=

50-315

' DOCKET NO.

UNIT SI:UTDOWNS AND POWER NEI)UCTIONS UNIT NAME D.C. Cook - Unit 1 2-13-84 DATE COMPLETED BY B.A. Svensson HEPORT MONTig JANUARY,1984 TELEPl10NE 616/465-5901 PAGE 1 of 2

$3 h

Licensee E**

l Causc & Cansective f'y

. N.i.

Date g

3g jgy livent gg n.

Atti.neto Preveni Recnisence

$E ji%g Report #

mO P

d 210 840106 F

0 F&H 4

N.A.

ZZ ZZZZZZ Reactor power reduced to 80% to meet steam generator secondary side chem-istry requirements. Reactor power was further reduced to 50% to remove the east main feed pump from service to check for tube leaks in the F-P turbine condenser. Reactor power was returned to 99.5% on 840107 and held there due to the allowable power limit restriction.

211 840123 F

184.1 B&A 3

84-002 CB IA Reactor / Turbine Generator trip due to an indicated low flow on reactor coolant loop 2 caused by an instru-ment valve on one of the reactor coolant flow meters leaking through when returning the flow meter to service. The Unit was kept out and cooled down to Mode 5, cold shutdown, to permit maintenance on RHR cooldown i

2 3

4 1: Foiced Reason:

Methml:

Latobit G Instinctiims 1

S: Schedulcil A-Equipmer.: I;ailuie (Explain) 1 -M.mual for Prepa::4einn of Data h-Maintenance of Test 2 Manual Serain.

Entiy Sheets fm 1.icensee C Refueling 3 Automatic Scram.

Event Repost (I.l?R) File INtIRIL D Regulatoiy Restiiction 4-Othes (Explain) 0161) lbCpesato l' raining & Liccuse lixamination F-Administ alive 5

G-Ope ational liisor (lixplain)

'Exlubit I - Same Smuce p8/17)

II Other (Explain) 1

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant sautdowns during the in accordance with the table appearing on the report form.

- report period.- In addition. it should be the scurce of explan.

If category 4 must be used, supply brief comments.

ation of significant dips m average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pertaining to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequent:al l

.' shut down completely. For such reductions in power level, report number, occurrence code and report type) of the tive the duration should be listed as zero, the r'tethod of reduction part designation as described in item 17 of Instrucuons 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 columrt should explain. The (LER) File (NUREG.0161). This information may not be Cause and Corrective Action to Prmnt Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully further 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 signiilcant reductionin power noted as not applicable (N/A).

for that calendu year. When a shutdown or significant power

reduction bepns in one report period and ends in another.

SYSTEM CODE. The system in which the outage or power reduction onginated sh' uld be noted by the tw'o digit eode of o

an entry should be made for both report periods to be sure all shutdowns or sigmficant power reductions are reported.

Exhibit G Instrucuens for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG.0161).

bet should be assigned to each entry.

Systems that do not fit any existing code should be designa.

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

of each shutdown or signiilcant 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 reduction from Exhibit I. Instructions for Preparation of Data Entry begms 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 entieria:

. or agnificant 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:

reducuan.' Forced shutdowns include these required to be e.g.. wrong valve operated through errort 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.

1 completed in the absence of the condition for which corrective ing the other components which fail, should be desenbed i

action was tien.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end of a report period, count only the time to the Components that do not fit any existmg code should be de-signated XXXXXX. The code 777777 should be used for end of the report period and pick up the ensuing down time in the followmg report penods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth oian hout 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 fasluon to amplify or tor 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 specific cause for each shut.

wn r ngni cam p wer reducuan and the immediate and

- REASON. :Cateaunze by letter designation -in accordance.

with the table appearing on the report form. If category H contemplated long term certac'ive action taken. if appropn.

ste. This column should also be used for a desenption of the must be used, supply bnef comments.

maior' safety.related corrective maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outsee or power reduction including an identification of i

REDUCING POWER.. Catesonze by-number dengnation the entreal path aetmty and a report of any smale release or

~

radioactmty or smale radiation exposure speettieally associ.

INote that this differs from the-Edison Electric Institute sted with the outage which accounts for more than 10 percent i TEED definitions of --Forced Pantal Outage" and " Sche.

of the allowable annual values.

duled Partial Outage." For these term >. eel uses a shange of For long textual reports continue narrative on separate paper 30 MW as the break pomt. For Iarger power reactors.30 MW and referen.e - the shutdown or power redu. tion for tt.t>

'is i..o small a change to warrant esplanation.

. narrative.

Wii 1a

~ ~ ~

~~"

DOCKET NO. 50-315 UNIT SitUTDOWNS AND POWER REDUCTIONS D.C. Cook - Unit 1 UNIT N AME DATE 2-13-84 JANUARY, 1984 COMPLETED gay B. A. Svensson REPORT MONTil TELEPflONE 616/465-5901 PAGE 2 of 2 "t.

Licensee Eg be.

.E E 3

) {Y Cause & Coneciive y

livent gg 83 Acnonto No.

. Dale Q

5g s

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$E 5

j;y3g Repo1#

(d O Preveni Recurrence.

F 6

isolation valve IMO-128. The Unit 211 (Continued) was returned to service on 830131 and reactor power increased to 79%

where it was being. held for secondary chemistry requirements.

1 2

3 4

1: Foiced Reason:

Method:

Exhibie G -Insieuctions S: Scheihileil A Equipmer.: Faihue(limplain) 1 Manual for Pacparation of D.na ll-Maintenance of Test 2 Manual Scram.

Entiy Sheets foi 1.icensee C Refueling 3 Automatic Scram.

Eveni Repost il 1 R) File INtlRI G.

D Regulatosy Hestiittion 4-Othes (lixplain) 0161)

E-Operato l' raining a license I:xamination F-Athninist rative 5

G Operational Esto IExplain)

Exhibis 1 - Same Somee es/Tl) 11 Other (Explain)

-q UNIT SHUTDOWNS AND POWER REDUCTIONS t

" INSTRUCTIONS :

This report should desenbe all plant shutdowns during the in accordance with the table appearing on the report form.

Ireport penod., in addition. It should be the source of explan-If catehory 4 must be used. supply brief comments.

J anon of sigruficant dips in average power levels. Each signi.

'ficant redaction in power !evel (greater than 20'6 reduction LICENSEE EVENT REPORT =. Ra'erence the applicable in average daily power level-for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) mportable occurrence pertainmg to the outage or power should be noted. even though the unit may not have ceen reduction.. Enter the first four parts (event year. sequentral l

f shut down completely. For such reductions in power level.

mport number, occurrence code and seport type) of the tive

the duration should be listed as zero, the method of reduction part designation as desenbed 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 Present Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be

' Cause and Corrective Action to Prevent Recurrence column immediately evident for 211 such shutdowns of course, smee should be used to provide any needed explanation to fully.

further investigation may be required to ascertam whether ur

' describe the circumstance

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 sigmilcant reductionin power n ted as not applicable (N/A).

for that calendar year. When a shutdown or sigmffcant power SYSTEM CODE. The system in which the outage or power reduction begins m one report pened and ends m 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 -

all shutdowns'or significant power reductions are reported.

Exhibit G Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG.0161).

l 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 shutdcrn cr :!;nificant power reduct:en from Exhibit !. Instructions for Preparation of Data Entr>

begms in one report period 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:

reduction. Forced: shutdowns include thase 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 mal.

J 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 fait should be desenbed -

/ action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

. DURATION. Self. explanatory. When a shutdown extends Components that do not fit any existmg code should be de.

beyond the end of a report period. count only the time to the ed HHXX. The code ZZZZZZ should be used for end or the report period and pick up the ensuing down time events where a component designation is not applicable.

in the following report periods. - Report duration of outages irounded to the nearest tenth o(an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVLNT RECUR.

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

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

period.

The column should include the specific cause for each shut.

down or significant power reduction and the immediate and.

REASON.' i Cai'8'irize by letter deugnation in accordance contemplated long term corrective action tamen, if appropn.

. with the table appearing on the report form If category 11 ate. This column should also be used for a desenption of the must he used. supply brief comments.

major safety.related corrective maintenance performed durtne METHOD OF SHUTTING DOWN THE REACTOR OR the outsee or power reduction including an identification ot REDUCING POWER. Catesonze ' by number designation the entreal path activity and a report of any smale release et radioactivity or single radiation exposure speettically assoes.

I ote 'that this, differs 'trom the Edistm Electrie Insuture sted with the outage which accounts for more than 10 percent N

teel) definitions of " Forced Parnal Outaae" and " Sche.

of the allowable annual values.

Juled Partial Outase." For these terms. I El uses Ahange of For long textual reports continue narrative on separate paper

~.'O MW 'as the break pomt." For larger power reactors. 30 MW

.md reference the shutdown or power redustion foi this t s too small J ihange to warrant e Aplanation.

narrative.

i i

(W77 '

~~

. ~. -, - -~,,. ~.,, -. + -

~

Docket No.:

50-315 Unit Names D. C. Cook Unit 1 Completed By:

G.

J. Peak Telephone:

(616) 465-5901 Date:

2/6/84 Pager 1 of 2 MONTHLY OPERATING ACTIVITIES - JANUARY 1984 Highlights:

The Unit entered the reporting period in Mode 1 with the

' reactor holding at the 99.5% power level due to the Allowable Power Limit restriction.

The Unit tripped on January 23, 1984

-due to Indicated Low Flow on Reactor Coolant Loop 2.

The decision was made to cool down and degas the Reactor Coolant System in order to repair a Pressurizer Enclosure Ventilation Unit and valve IMO-128, (RHR suction from RCS).

These repairs were completed and the Unit was subsequently returned to service.

Significant power reductions occurred to leak check the East Main

-Feedpump Turbine Condenser, and due to secondary side chemistry requirements.

At the end of the reporting period the Unit was holding at the 79% power level, due to secondary side chemistry requirements.

' Total electrical generator for the month was 575,230 MWH.

Summary:

1/4/84 The Control Room Fire Detection System was declared ope.able at 1210 hours0.014 days 0.336 hours 0.002 weeks 4.60405e-4 months .. It had been inoperable at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months on 8/24/83 pending completion of functional testing of the fire detection system.

.1/6/84 Power was reduced-to 80% at 1329 hours0.0154 days 0.369 hours 0.0022 weeks 5.056845e-4 months to meet steam generator secondary' side chemistry requirements.

1/7/84 Power was further reduced to 50% at 0520 hours0.00602 days 0.144 hours 8.597884e-4 weeks 1.9786e-4 months to remove the East Main Feedpump from service to leak check the turbine condenser.

Power was returned to 99.5% at 2118 hours0.0245 days 0.588 hours 0.0035 weeks 8.05899e-4 months and held there due to the Allowable Power Limit restriction.

1/12/84 The fuel handling area exhaust-fans, HV-AFX-1-and 2 were declared-operable at 1116 hours0.0129 days 0.31 hours 0.00185 weeks 4.24638e-4 months .

They had been inoperable since 1321 hours0.0153 days 0.367 hours 0.00218 weeks 5.026405e-4 months on 11/2/83.

1/13/84 Power was reduced to 90% at 2329. hours for routine turbine valve testing.

1/14/84 Power.was increased to 99% at 0248 hours0.00287 days 0.0689 hours 4.100529e-4 weeks 9.4364e-5 months and held there due to the Allowable Power Limit restriction.

AB Diesel _ Generator was inoperable from 1910 hours0.0221 days 0.531 hours 0.00316 weeks 7.26755e-4 months on 1/14

to 2205-hours on 1/16 due to a malfunction of the electrical overspeed trip circuit.

Docket No.:

50-315 Unit Namn D. C. Cook Unit 1 Corpleted By:

G. J.

Peak Telephone:

(616) 465-5901 Date:

2/6/84 Page:

2 of 2 w

1/23/84

.The Unit tripped at 1350 hours0.0156 days 0.375 hours 0.00223 weeks 5.13675e-4 months due to an indicated low flow on Reactor Coolant Loop 2 caused by an instrument valve on one of the reactor coolant flow meters leaking through when returning the flow meter to service.

1/24/84 Reactor coolant system'being cooled down.

Entered Mode 4

- at 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months .

1/25/84' Entered Mode 5 at 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months .

1/29/84~. Reactor coolant system heatup started with Mode 4 entered fat 0358 hours0.00414 days 0.0994 hours 5.919312e-4 weeks 1.36219e-4 months .

Entered Mode 3 at 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months .

. 1/30/84-The. Reactor went critical at 2246 hours0.026 days 0.624 hours 0.00371 weeks 8.54603e-4 months .

1 1/31/84

- Mode'1'was entered at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months .- The main turbine was

< rolled at 0453 hours0.00524 days 0.126 hours 7.490079e-4 weeks 1.723665e-4 months .-.The main generator was paralleled to-the grid at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

~

e, The Control Room Cable Vault Halon System remains inoperable as of.1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on 4/5/83.

The backup CO System for the 2

^^

Control Room Cable Vault remains operable

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-DOCKET No.-

50 - 315

~~

UNIT NAME-D. C. Cook - Unit No. 1 DATE 2-13-84

-COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901

'PAGE 1 of 2

. MAJOR SAFETY-RELATED MAINTENAhCE JANUARY, 1984 M-lL LAB diesel auxiliary jacket water pump had a abnormal rubbing

- noise. Investigation revealed bad motor bearings. The bearings

-were. replaced.,

~

. M-2 The north waste gas. compressor discharge valve, #WD-221N, was leaking by..

The valve was disassembled, diaphragm replaced and reassembled.

M-3'

' MRV-222,. #2 S/G; steam stop trip valve was disassembled. The stem,iplug,. seat and packing were replaced. New gaskets were installed and the valve was reassembled and tested.

~ M The: south waste gas compressor was compressing gas to the gas

-decay tanks at a very slow rate. The defective diaphragm on the suction valve was replaced.

M-5 QRV-61, alternate charging line to loop #1 cold leg failed to open.' The diaphragm in the air operator.was replaced. A retest was. performed'and the valve _was returned to service.

M -The south waste gas compressor's pumping capacity wae below (normal. ~The impeller clearance was adjusted. The compressor

. tested satisfactorily add was returned to service.

lM-7 1-CD diesel lube oil heater pump had an abnormal noise while

~in' operation. The pump was replaced with a new one and a function test was performed.

' M QRV-162, air operated 75 GPM letdown orifice isolation valve Twas found with air' leaking'around the diaphragm.- The diaphragm was replaced, a retestiperformed',.and the valve was' returned

'to service.

M-9

.NKV-151, -pressurizer power operated relief valve leaked by.

-The valve was disassembled replacing the plug,~1 stem, packing, fseat ring and gaskets..Upon reassembly the valve was tested

~

-and returned'to' service.

M-10

.lM0-128,: loop 2 hot leg to RHR' pumps'had a packing leak.

In-vestigation revealed the yoke. assembly to be damaged by boric acid and steam from ~ thel packing leak. The yoke assembly was replaced. The valve was repacked, tested and returned to service..

I 7

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i DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1

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. COMPLETED BY B. A. Svensson DATE 2-13-84 s= '

TELEPHONE (616) 465-5901

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PAGE 2 of 2 j

MAJOR SAFETY-RELATED M,.'.NTENANCE Y

JANUARY. 1984-c p,.

~

C&I-l /- ~ Co'ntrol rod shutdown bank "d' rod J-3 position indication was 12 steps from demand. The position of rod J-3 was calculated per **12.THP 6030' IMP.038. The indicator amplifier was found

,7,

-cto be out of-calibration,~ with the rod in step with demand.

~

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The in'dicator amplifier for rod J-3 was recalibrated.

C&I-2,

. Emergency diesel generator "AB" received a spurious engine e

overspeed' trip when the generator room door was opened.

Thorough troubleshooting revealed a defect in the Dynalco

tachometer unit. A new tach. was installed and calibrated.

Th'e engine was then started and was tripped by an overspeed

' signal to verify correct operation.:

C&I. Steam generator #4~ steam flow instrument MFC-141 read 0.5x106 4

PPH with no steam flow. Recalibration of the square-root ex-

q '

tractor module returned the inctrument to operable status.

C&I-4:

. Normal' reactor coolant system charging valve, QRV-62, did not open properly.upon demand.

"Asco" solenoid valve fr QRV-62

. was.. replaced.

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C IMOMNA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465 6901 February 13, 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 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of January,-1984 is submitted.

Sincerely, LO W. G. Smith, Jr.

Plant Manager 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.11. Bennett J. D. Huebner

'J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Scietzel PNSRC File L

INFO Records Center g>

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ML20080T751

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