Text

Monthly Operating Rept for Jan 1982
	ML20042A434
Person / Time
Site:	Cook
Issue date:	01/31/1982
From:	Might A; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20042A430	List: ML20042A429; ML20042A434;
References
	NUDOCS 8203230415
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CPIR.C;C DATA RIPCR-DCC:m NC. 50-316 DATI

_J a me rv 31, 1982 CO.NL*LITIC ?.Y A - Micht 6in a -5901 TILI?.9CNI

.C.?IRATING S ATUS Not:8 Donald C. Cook P1 ant 2

1. Uni Name:

Januarv 1982 y_, g,pog y. dad:

3391

3. U~ M T'-f Powe @iWt):

1133

4..%

8*-R::i ;(Csoss 5 We):

1100

5. Dests:t se==:i=1 R::in;(Nec 51We):

IIIR

4. L Depend:ble Caped:7 (Gross 31We):

1082 T. M*= Depd:hl C:p:=i:f(Nec MWe):

S. If c v Cain C:paci:y P'd ;s (It: s Nu.=her 3 Through 7) Sinc = L:s:Repor:. Give Re sens:

9. Power Levd To Whi=h Rer:::.. d,If Any (Net MWe):

10. Rz: sons For Re-+cs.If Asf:

nis Month Y:.<o-Cata C c = r- %

744 7aa 35,608

11. Ecurs != Repor.'ag P=ied 736.1 24,761.I 736.1

12. Nar..he Cf Hoc:s Re.::ce W:s Cd"=1 0

0 0

13. Recar Rese:ve Shu:down H:.::s

14. Hoc:s Cee=.,e ca.U =

733.1 733.1 23.954.1 0

0 0

15. Ur.it R.se:ve S*tutdown Ec==

2.295,944 2.295.944 76.356,765 lo. Cross ne==:1 I:::;y Ce==::d QiWE) 750,110 750.110 24.457.910

17. Cross IIee:i=1 I=egy Ge===::d t,MW:Il 722,724 722,724 23.566.865

13. Net E+12:=;y Cen==: d OtW~ca-98.5 98.5 71.9

19. U=ir series.:s::=r 98.5 98.5 71.9 l

23. Uni: Ar.-il:oiH y F:c:or 89.8 89.8 67.2 l

21. UM: C:=acity 7:::=r (Usi=; MDC Nee) l

'2. t.'ait Cacacity F:::ce (Usin; DIR Net 88.3 88.3 66.4 1.5 1.5 13.8

'.3. Uait Fore:d Cu::ge R:c,

4. L=td.m:s Scheduled Over Nec 5 Mon:hs (Type. D:te.: d Oc=: ion of I:r.h :

S. If 5.::: Cowrt At Ind Of ?.eport ?=iod. Istim::ed D:ce ci Star:as:

. 25. Units la Tes: S :: :s !Pnor to Ce==di Cp =:fest:

Fore =st Acieved

~

INITIA L C?.I-*CA UTY

~

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INITIAL I* IC 2:Cin CO.*.t.*.; r.C:A: O? IRA 7:CN Cl O

R

~-

AVE.4 AGE DATLY UN!T POWER LEVEL 00CKET-NO. 50-316 UNIT 2

DATE January 31, 1982 CCMPLETED BY Ann ~Might TELEPHONE 616-465-5901 MONTH January, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 936 17 335 2

650 18 983 3

1024 19 1088 4

1067 20 1088 5

1065 21 1088 6

749 22 1089 7

662 23 1088 8

1061 24 1087 g

1062 25 1084 10 1056 25 1083 l

11 1049 27 1084 12 1067 23 1016 13 1067 29 508 14 1069 30 946 15 1070 31 1081 16 762 INSTRUCTICNS l

On this format list the average daily unit power level in MWe-Net for each day in the repor-ing month. Ccmoute to the ne= rest wnole megawatt.

DOCKETNO. 50-316 UNITSilU1 DOWNS AND POWER REDUCTIONS i

UNITNAME D.C. Cook - Unit 2 DATE 2-12-82 s'anuary, 1982 COMPl.ElED NY B.A. Svensson REPORT HON 111 1El.LPilONE (616) 465-5901 PAGE 1 of 2 "t.

m e

c

.E E

}

Y}

Licensee 5 t,

{w't Cause & Cansective 8

Attism to

@ sg livent p

gO N...

Dale g.

gIg H

gE j;jj g Repost #

to O Prevent Hecusscuce a

g 5

104 820101 F

0 B

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 56% to re-move the West main feed pump turbine from service to check feed pump tur-bine condenser for tube leaks. One leaking tube was fo'und and plugged.

Reactor power returned to 100% on 820103.

105 820105 F

0 A

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 56% to re-move the West main feed pump from service to repair weld leak in the feed pump suction strainer drain line.

Reactor power was returned to 100% on 820108.

106 820116 F

10.9 H

3 N.A.

ZZ ZZZZZZ Unit tripped from a turbine trip.

The exact cause has not been deter-mined.

It appears that the cause was a closed valve in the impulse line to l

the' stator cooling water low-flow in-strument combined with low ambient temperatures.

2

.I 4

14 1 enceal Heason:

Metinal:

Enhibit G Instinctions S: Scheilnical A l?iluipment l'ailme (I nplain) 1 Mam.al for Picpasation of Data ll-Maintenance oi Test 2 Manual Scram.

Entsy Slicess fos 1.icensce C Reincling

.1 Antomatic Scram.

livens Hepini (l.liR) I ile INilRIE D Regulaiosy Resisiction l Other (!!xplain) 0161)

ILOpesaios l'eaining & 1.icenw l!xaminallon 1: Asiminisisative G Operational Enos IExplain) lishibit 1 Same Somce I'l/17 )

11 Othes (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns dunng de m :::ordance with the tecle appearms on the r port form.

report penod. In addinon. It should be the source of explan.

If :stegory 4 must be used. supply bneicomments.

atton of sigmncant dips m average power leveis. Each sigm.

5:2nt redu:non m power level (grester than 20% reducuan LICENSEE EVENT REPORT =. Reference the spph:: ele m 2verase daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) teportable oc:urrence pertsmmg to de outsge or power should be noted, even though de umt may not have been reduction. Enter the Erst four parts (event year. sequennal l

shut down completely. For such reductions in power level, report numoer, oc:unence code and report type) of the Sve the duranon should be !!sted as :ero, the method of reducuan part deugnation as desenbed in item 17 of Instrucuons for should be listed as 4 (Other), and the Cause and Correcuve Preparzuen of Data Entry Sheets for Licensee Event Report Acnon to Prevent Re:unence column should explain. The (LER) File (NUREG4161). This informanon may not be Cause and Correc=ve Action to Prevent Recurrence column

=tmediately evident for all such shutdowns, of course, smce should be used to provuie any needed explanation to fully further mvesugation may be reqmred to ascertam whether or desenbe the circumstances of the outage or power reduction.

not a repor:2 ele occurrence was involved.) If the outage or power redueden will not result in a reportsele oc:urrence.

NUMBER. Th:s column should indic:te the sequent:21 num-de p sitive mdication of its lack of correisuon shou!d be oer assigned to each shutdown or sigmilcant reducuan m power noted as not applicable (N/A).

for dat calendar year. When a shutdown or ugmncant power SYSTEM CODE. The system in which the outsee or power reduction begms in one report period and ends m another.

an entry should be made for both report penods to be sure redugnon ongmated should.se noted by the two digtt eode et til shutdowns or sismilcant power reducuens are reported.

naunoit G. Instrucuens for Preparanor. or Data natry sneets

'intil a unit has ach'ieved its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG4161).

bar should be assigned to each entry.

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

ted XX. The :cde ZZ should be used for dose events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or ugnincant power redueden. Report

s year. month, and day. August 14.1977 would be reported COMPONENT CODE. Sele:t the most appropnate component u 70814. When a shutdown or ugmficant power reducuan from Exitibit !. Instru:ucas for Preparanon of Data Entry begms m one report pened and erds m snother, an entry should Sheets for Licensee Event Report (LER) File (NUREC4161).

be made for both report penods to be sure all shutdowns using the followmg critiena-or ugmn:snt power reducdons are reported.-- -

TYPE. Use "F" or -S" to indicate either " Forced" or ~3che.

duled." respeedveiy, for each shutdown or significant power B.

If not a ecmponent failure, use de related component:

reducuen. Forced shutdowns include those required to be e.g., wrong valve operated through error: list valve as mitiated by no later than the weekend following discovery component.

i of an off-normal condition. It :s recogni:ed that some judg.

ment is regtured m :stegonzmg shutdowns in this way. In C.

If a chain of failures occurs, the Srst 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 correcdve ing the other components wiuch fail, should be desenbed acdon wu taken.

under the Cause and Correcdve Acdon to Prevent Recur.

rence column.

DURATION. Self-explanatory. When a shutdown extends Components dat do not fit any existmg : ode should be de.

beyond the ene. or a report penod. count only the uma to the ed MM T'u 2 N'P"I' M 'a M h cnd or the report pened and pick up the ensumg down time events where a component deugnation is not appiicaole.

m the followmg recort penods. Report durauon of outages ruunded to the nearest tenth of an hour to factlitste summanen.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the geners.

RENCE. Use the column in a narranve fastuon to ampiify or tar was on line should equal the tross hours in the reportmg explam the circumstances of the shutdown orpower reducuen, penod.

The column should include the seccific :suse for each shut.

down or ugmne:nt power reducnon and the immediate 2nd REASON. Categonze by letter deugnanun :.n accorcance contemolated long term correcuve acuan taxen. if acpropn.

with the table socearmy un the recort form. If :stegory H 7

i mn'should also be used for a desenotion of the must be used. suopiy bnet eumments.

maior safety.re!:ted correcuve mamtenance performed dunna e urage r p wu recu: don meludinz an :dentific: tion of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Cateson2e ev numner deurnsuun

ne entte:1 path acuvny anc 2 report or any ungle reiease of r:diosenytty or smale racistion excesure scestdestly assce:.

I%e that this differs from the Edison Eleetne Insutute sted with the outsae wruch ac cunts for more than 10 :ereent (EE!) desmuons of " Forced P:ru:1 Outare" anc "Sene.

oithe 2ilo*30le 2nnual vslues.

au!ed Partial Outage ' For these tema. !-El uses a shanze or For long textual recons contmue narranve on sec2r:te paper

.0 MW ss the creak ;wnt. For iarper power resetors.30 MW nd rereren : me shurcown or power recusuun im um

s im smati a hanae to warrant npianation.

narrat:ye.

DOCKETNO. 50-316 UNIT SilU1 DOWNS AND POWER REllOC110NS

~

UNIT N AME D.C. Cook - Unit 2 11 ATE 2-12-82 B.A. Svensson REPORT MONTil January, 1982 COMPLE1ED BY (616) 465-5901 1El.LPilONE PAGE 2 of 2 "E

i n nsee E v, h,

.E E

'g iff Cause & Cossective 3

Action to N. i.

Date g

gg

,ysg livent y,3 gU g6 Heport #

to O Prevcsit Recusscuce H

g 6

107 820128 F

0 A

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 42% due to failure of the North condensate booster pump motor and high vibration on the middle condensate booster pump motor.

The middle pump motor was balanced and reactor power re-turned to 100% on 820130.

I 2

3 4

1: l'os ceil Reason:

Melluxt:

lixhibit G - Instinctiims S: Solicif ulcal A 1 quipment l'alluse (Lxplain) 1 -Manual fos Preparation o1 Data 114taintenance of Test 2 Manual Scram.

I!ntiy Slicets fin I.icensee C Refueling 3 Automatic Scram.

I! vent Repint ll.l!Ril:ileINURIE D Itegulatosy itestsiction 4 Ollies (Explain) 0161)

!! Opesato l'saluing & License lixamination 1 Ailsninist ative 5

G Opesational linos llisplain) lisliibit 1 - S.ame Somce p8/171 ll Othes (fixplain) l

UNIT SHLTDOWNS AND POWER REDUCT10NS INSTRUCTIONS This resort should desenbe all plant shutdowns dunng 1e in se:ordance with the table appearmg on the report form.

report penod. In addiuon. tt should be the source of explan.

If:stegory 4 must be used. supply bneicomments.

mion of sigm6 cant dips m sverage power leveis. Esd sizni.

fi:2nt reducuan m power level (3 rester than 20% reduction LICENSEE EVENT REPORT =. Reference the applicaole

~

m sveraae daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) re; nsble oc=nence penamng to the outage or power could be noted. even though the unit may not have been reducuen. :nter the nrst tour parts (event year. sequennal snut down completely. For' sus reductions in power level rep rt number. oc:urrence code and report type) of tne five l

the dursuon should be listed :s zero, the method of reducuen pan designation as desenbed in item 17 or Instrucuons tor should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Act:en to Prevent Recurrence column should explain. The (LER) File (NUREC.0161). T*rus informanon may not be Cause and Correcuve Acuan to Prevent Recurrence column immediately evident for all such shutdowns, of course. smce should be used to provide any needed explanation to fully turther mvestigation may be required to ascertam whether or desenbe tne :ircumstances of the outage or power reducuen.

not a reportaole occurrence was involved.) If the outage or power reducuon will not result in a reportsble occurrence.

NUMBER. This column should indic:te the sequential num, the pouuve indicattert of this lack of corniauen shou!d be oct assigned to each snutdowTt or signiBeant reduction m power noted as not applicable (N/A).

for that esiendar year. When a shutdown or ugmncant power SYSTEM CODE. The system in w is the outage or power reduction begms in one report pened and ends m another, reduction ongmated sho' uld be nota by the tw'o digit code of an entry should be made for oath report penods to be sure Em C. Wnwem 6 P%m m' N W S'm s11 shutdowns or sigmn:2nt power reducuens are reported.

Until a unit has achieved its first power generation, no num-for Licensee Event Report (LER) File (NUREC.0161).

ber should be assigned to ea:h entry.

Systems that do not fit any existmg code should be dengna.

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

of each shutdown or signincant power reducuen. Report ss year. month. and day. August 14,1977 would be reported COMPONENT CODE. Se!e:t the most appropriate :omponent as ~70814. When a shutdown or ugnificant power reducuor.

from Exhibit !. Instructions for Preparanon of Data Entry begms m one report pened and ends in another. an entry should Sheets for Licensee Event Report (LER) File (NUREC.0161).

be made for both report penods to be sure all shutdowns usmg the following :ntienat or s:gmncant power reductions are reported.

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

duled." respectively, for each shutdown or signiGcant power B.

If not a cornp9tye '.ilure. use the related component:

~

reducuon. Forced shutdowns include those recuired to be e.g.. wrong vahe operated through erron list valve as mitiated by no later than the weekend following discovery comoonent.

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

ment is required in estegorizmg shutdowns in this way. In C.

If a chain of fatlures occurs, the first component to mai.

l general, a forced shutdown is one that would not have been function.hould be listed. The sequence of events.includ.

j completed in the absence of the concition for which corrective ing the other components which fail, should be des:nbed l

action was taken.

under te Cause and Correcuve 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 ot 2 report penod, count only the time to the signated XXXXXX. The code 777777 should be used for end or the report penod and pick up the ensumg down ttme events where a component designation is not appli:2cle.

m the followmg report penods. Report durauen of outages ruunded to tne nearest tenth of an hour to fac:litate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

_he sum of the total outage hours plus the hours the genera.

t RENCE. Use the column in a narranve fasinon to ampiify or tor was on line should equal the gross hours m the reportmg explain the circumstances of tne shutdown or power reducuen.

penod.

The column thould include the see:tdc :suse for each shut.

dowfl> sizm6 cant power reduction and the immediate and REASON. Categorue by letter designanon in accordance contemoisted lont term correcuve acuen taken, if appropri.

l ctth the taole accearmy on the report form. If :stegory H 3,,,

7rus :oluma should also be used for a desenotion of the must ne used. suppiy bnet eumments.

major safety.rel:ted corrective mamtenance performed dunna L

utage or p wer reducuen mefudin; 2n idenu8 canon d METHOD OF SHUTTING DOWN THE REACTOR OR M * *Y *"d *

E " * *"Y N ' N 25# #

REDUCING POWER.

Categorue ey number desiznsuun radioacuvity or smale radistron exposure spectdesily asscet.

l INme that this differs rrom the Edison Eleutne Institute ated with the outage v+ch accounts for rnere tnan 10 percent i EE!) dedmtions of " Forced P.n:21 Outsge" and -Sche, of de allowsole annuat..tlues.

uled P:rtial Outage.' For these tenn>. EE! uses a change at For long textual reports eentmue narranve on secarste paper

.0 MW ss the areaA pumt. For larger power resetors.30 MW

nd reterense tne shutdown or power recu uun im uun

s w small a enanne to wanant espianation.

narranve.

Docket No. :

50-316 Unit Name:

D. C. Cook Unit 02

~

Completed By:

C. E. Murphy Telephone:

(616) 465-5901 Date: February 8, 1982 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - JANUARY, 1982 Highlights:

The Unit entered this reporting period operating at 100% power.

At 0656 hours0.00759 days 0.182 hours 0.00108 weeks 2.49608e-4 months , on Friday, January 1, a reduction in power was started to remove the West Main Feed Pump from service to make repairs to a suspected leak in its condenser. The unit was at 56% power by 0510 on Saturday, January 2.

The West Main Feed Pump was removed from service and one ccndenser tube was found to be leaking.

After the leaking condenser tube was plugged a unit power increase was started at 1033 hours0.012 days 0.287 hours 0.00171 weeks 3.930565e-4 months on Saturday, January 2, and the unit was at 100% power at 0855 on Sunday, January 3.

At 2243 hours0.026 days 0.623 hours 0.00371 weeks 8.534615e-4 months on Tuesday, January 5, the unit was again started down in power to remove the West Main Feed Pump from service to repair a weld leak in the feed pump suction strainer drain line.

The unit was at 56% power by 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months on January 6.

The necessary repairs were completed on the West Main Feed Pump Suction Strainer and a power increase was comenced at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months on January 7.

The unit was returned to 100% power at 0125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months on January 8.

At 1753 hours0.0203 days 0.487 hours 0.0029 weeks 6.670165e-4 months on January 8, both Essential Service Water trains were declared inoperable due to a missed 18 month surveillance on the Component Colling Water Heat Exchanger Outlet Valves. A power reduction was started to comply with the requirements in Technical Specifications.

One of the CCW valves was tested satisfactorily at 1837 hours0.0213 days 0.51 hours 0.00304 weeks 6.989785e-4 months and the power reduction was stopped.

The unit was returned to 100% power at 1847 hours0.0214 days 0.513 hours 0.00305 weeks 7.027835e-4 months .

l At 1336 hours0.0155 days 0.371 hours 0.00221 weeks 5.08348e-4 months on January 10, the condenser de-icing outlet temperature 0

limit of 56 F was reached and power was reduced several times by 2 to 4%

to maintain this temperature within limits.

Some difficulty was encountered l

in getting out of the de-icing mode due to the problems with circulating water discharge valves.

The unit was returned to 100% power at 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months on January 11.

On January 16, at 1717 hours0.0199 days 0.477 hours 0.00284 weeks 6.533185e-4 months , the unit tripped from an unknown cause.

l Following the unit trip the dose equivalent I-131 spiked to 2.04 mei/gm which exceeded the T/S limit of 1.0 mci /gm.

This necessitated declaring an " Unusual Event", which was secured at 0740 hours0.00856 days 0.206 hours 0.00122 weeks 2.8157e-4 months on January 17.

The reactor was taken critical at 0112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months on January 17, the unit paralleled with the system at 0412 and 100% power was achieved at 1230 on January 18.

~

l At 1910 hours0.0221 days 0.531 hours 0.00316 weeks 7.26755e-4 months on January 28, a power reduction was comenced on the unit l

due to high vibration on the Middle Condenser Booster pump. At 0648 hours0.0075 days 0.18 hours 0.00107 weeks 2.46564e-4 months on January 29, the power was leveled off at. 42% and repairs were started

Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

C. E. Murphy Telephone:

(616) 465-5901 Date:

February 8,1982 Page:

2 of 2 Highlights:

(continued) on the Middle Booster pump.

At 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on January 29, the balancing of the middle pump was completed and power was increased to 100% by 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on January 30.

Total electrical generation for this month was 750,110 mwh.

Summary:

i 01-17 The No. 3 Steam Generator Flow Channel MFC-131 was inoperable for a 33.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for calibration.

01-19 The West Containment Spray pump was inoperable for a 47 hour5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months period to repair a cracked weld in the pump suction piping.

01-21 R-15 (Condenser Air Ejector Monitor) was inoperable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to replace the detector.

01-22 The West Comoonent Cooling Water Train was inoperable for a 35 hour4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months period for repairs to CM0-420 and CM0-429.

R-33 (Gland Seal Exhauster Monitor) was inoperable for a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months period due to a stuck check source.

01-27 The No. 3 Boric Acid Transfer Pump was inoperable for a 2.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to unplug a pressure gauge line.

01-30 The No. 3 Steam Generator Flow Channel I was inoperable for a 20.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period due to instrument malfunction.

01-31 The SG-21 (Circulating Water Temperature Recorder) was inoperable for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period due to skipping points.

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 2-12-82 COMPLETED BY B. A. Svensscn TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1982 M-1 The air line to the upper containment volume airlock door (fcr testing the seals) was leaking at a fitting.

Cut the line, rethreaded the line, installed threaded line and rewelded.

Had necessary NDE performed.

M-2 The west CCW heat exchanger outlet valve, CM0-420, would not close. The valve stem was binding.

Machined the valve housing cover to provide sufficient clearance.

Had the valve tested.

M-3 The west CTS pump suction strainer had a weld leak.

Had NDE (PT, UT and RT) performed to determine extent of problem.

A 6" circumferential crack was indicated.

Ground out the affected portion of the weld and rewelded.

Had necessary NDE performed and completed a hydrostatic test.

A " boat" sample of the cracked area was sent out for lab analysis.

M-4 The west RHR heat exchanger CCW outlet valve, CM0-429, would not function properly.

The valve was binding.

The butterfly valve was replaced, tested and returned to service.

C&I-l Channel IV steam pressure indicator (516A) for No. 21 Steam Generator was indicating 29 PSI lower than the other two channels. The loop was recalibrated and returned to service.

C&I-2 MFC-131, Steam Generator No. 3 protection set steam #10w did not provide indication at 2.5% reactor power.

The protection set bistables associated with MFC-131 were placed in the trip mode. The transmitter's output sig-nal was monitored for a 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months period.

During the monitoring period the reference legs appeared to have refilled and normal signal levels re-turned.

The output signals were verified and the channel's bistables were returned to normal.

C&I-3 Circulating Water Pump No. 23 would trip following 11 minutes of operation.

Relay 5183 RLY420 (IAC66A1A) was tested and found to actuate with a test current of 4.5 amp.s..

The relay was recalibrated to the correct value of 5.5 amps.

C&I-4 Heat Tracing Circuit 235, Boron Injection Tank (BIT) inlet piping, alarm sensing bulb was found detached from the piping.

The bulb was relocated and mounted properly and the pipe reinsulated.

J

ML20042A434

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