Text

Monthly Operating Rept for Apr 1983
	ML20076H060
Person / Time
Site:	Cook
Issue date:	05/04/1983
From:	Will Smith, Tetzlaff A; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8306160384
	Download: ML20076H060 (7)
	v • d • e

,, e. m.;_

OPERAT:NC DATA RE?CRT 1

...s..".

. s D C C:.I T N O.

50-316 DATI 6 4 R3 COSi?L2 IO IY A.L. Tetzlaff TIL.I?.9CNE (616)465-5901 I~

o?in !NG s ATus D.C. COOK UNIT 2 Not:5

1. Uni Name:

APRIL 1983

2. Reporth; ?: dad:

3411 3.1.!cassed The--! ?ower C.iW:):

1133

4. N :ceplate ?.=i. ;(Csoss StWe):

1100

5. Desi;= Zie=d=1 R::in;(Nes 51We):

1118

6. SM s== Depend:h!< Csp:ci:f (Cross 3!WS): _

T. Siaxi==m Dep-d ' le C:p:=i:f (Nes 31Wer.

_.1082

8. If Ch:n;:s Oc=r in C:paci:7 Ruh;s (1::=s Nernhe: 3 Th:ou;h 7) Sine: L:s: Report. Give R: sons:

9. Power f. eve! To Whhh Res= iced.!! Any (N : 3:We):

10. Re: sons For R.

dons.lf Asy:

y,,,

\\' '

x This Morith Yr.4o. Data Cu. =hdve

/

719 2.879 46,703

' 11. Hours != R:per h: P::fod s

12. Fur..her of Ho=s R==: r Wzs Cridd.1 s 719 2,401.5 11 ';1a o O

O

13. Rector Rese:ve Shu::iown E d2 0

719 2,321.8 32.283.5

14. Ho=s Gene =:sr Cn-Li=s

15. U:!: R: serve ih:tdown Ho=s I

10 0

0 I

?,428,234 7.545.598 103.809.829 a. 16. Cross The==r.! E ::;y C4.:=:-d (YWM)

J._ 832.360 2.500,340 33.458.090

17. ~ross Ile==i=!Imer;y Ce:-=::d ('tWH) 3

13. Net II::=i:dl Z : ;y, Gene =::d C.diri) -

'785.489 2.414.409 32.254.?01 100 80.6 73.5

19. Ur.it Servid Re:ar n

\\ ~~

80.6 73.5 100

20. LW:indshi!I.~ F:c'oy s

a ~101,0 77.5 69.3

-I. Uni: C.:=d:.- F=::or Wsin: StrC Net) 76.2 68.4

. ~ UndChidt/.'-c:or(Usin; DER.4ett J J 9.3 O

1.1 13.1

23. Unir.cor=d 'id:::e Ret.

f' m 24. Shutdowns Scheduled Over Nex: 5 Mor.:hs (Type. O te. :nd Du=:fon of I:ch1:

~

SURVEILLMCF'0![TAGF SCHFni!! Fn FOR JUNE 1983 P

x t

,q,

y

5. If Sh:: Dow t A: End Of Reporr ?::iod. Isti:.yed D:te'of Star:::p:

,i 4

. E Units In Tes: 5:::us (Prior ta C:=r:::=i:1 Ki:=tient:

Fore =st Achieved I

INITIAL CRIT *CALITY

~

s -

IN;TIAL II.ICTR:C; Y

~

s CON l.;I?.CA L O?!?.A 7:CN g

.,A F

j

,I O

t l

PDR.

x s s..-

r,-

j c\\

I g '

w.,

,.__,,[,..

..j _ _ _ _, _,,

~-

._,__,____,.n.,

AVERAGE DAILY UNIT POWER LEVEL 3

'~

~

DOCKET NO. 50-316 UNIT 2

DATE 5-2-83 3

COMPLETED BY A.L. Tetzlaff I

TELEPHONE (616)465-5901 MONTH APRIL, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1104 17 1086 2

1092 18 1104 3

1084 19 1105 4

1103 20 1103 5

1098~

21 1102 6

1102 22 1096 7

1102 23 1099 8

1101 24 1106

~

9 1094

~

25 1103 10 1103 25 1023 11 1093 27 1049

- 12 1102 28 1065 13 1101 29 1062 14 1104 30 1085 15 1093 31 16 1060 INSTRUCTIONS On this femat list the average daily unit power level in MWe-Net for each day in the reporting month.

Ccmpute to the nearest whole megawatt.

IMM?KET NO. 50-316 IJNIT SilUIDOWNS AND FOWL H HEllUCllONS UNII NAhlE D.C._ Cook - Unit 2 DATE 5-12-83 COnfPt ETEn ley B. A. Svenssen HliPOR'l hlONill April, 1983

'IEl.ErilONii 616/465-5901 SHEET 1 of 1 i

3E 3

)N' I icensce 5-e,

p;.

Cause a Cansettive No.

Dine Q

Eg s

js&

livent gy

o. ?

Atis.no t.:

3 ;p, g Hep.nl #

<2 0

!O Psevent Hernesence i--

e o

co 124 830426 F

0 A

4 N.A.

CH HTEXCH Reactor power reduced to 80% to re-move the "A" - string of high pres-sure heaters from service to repair suspected tube leaks in Heater 5-A.

Reactor power was returned to 100%

the same day with the heater string remaining out of service. A total of four tubes were plugged. The 4

heater string was returned to ser-d vice on 830430.

I 2

3 4

lh l'osrcil Heason; hicilioil:

listolus G - Inse nstssons S. Stlicilnical A I quipmes. 1 ailuse (l;xplain)

I hlannal los Psep.n allon of Inas.a 11 hiaintenance ni Tess 241 annal Scs am.

Entsy Sliceis los I.sicusee C Helucling

.l-Antonutic &.sm.

liven Repost il l'Itilite INill(I G-D llegulaeney Hesteitsion

-l Otises ll:xplam)

(1861) 1: Opesaios I'saining & Iitense I:xaminaison 1: Ailminisis.iisve 5

G Opesafional I esos ll!spl. shin laintut 1 - Sasuc Souo c p8/l/)

11 Ollies i t;spl.un t

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Th:s report saould desenbe 211 ;iant shutdowns dunn; me a n:ct:2n;e with de t2:le ac;eanng on the report form.

report penod. In addiucn. tt should be de sour:: cf explan.

If stegory a must be used. suppiy br:ef ::mments.

anon of sig:unc:nt dips a 2verage power levels. E2:n 1:pt-LICENSEE EVENT REPORT :. Referen:e de appli:2ble fi:2nt reduenon m power level (greater can 20"c reduction m aver 2p daily power level for de preceding 24 hnun) reportable oc:;rrence pen 2mmg to de outage or power

* 'CU-20

'**U report numcer,'c::urrence : de and report type) or me ::ve* F could be noted, even dough 2e umt may not have :een l

snut down completely. For su:n reduenens in power '.evel.

tne duration should be listed as zero the method of reducuon part denpat:on as des:nbes in Item 1, or, Instruenons tar should be listed as 4 (Other) 2nd de Cause and Corre:nve Preparanon of Dats Entry Sheen for L::ensee Event Repcrt Acnen to ?revent Recurrence :clumn should expism. The dEM Ee @CREg!64 Thn mfonnanon may not :e Cause and Corre:nve Action to Prevent Recurrence column t= mediate!y ev: dent ror 211 such shutdowns, of coune. since should be used to provide any needed explanation to fully ruttner mvettgation m2y be recutred to ascertam whether or desenbe the circumstances of de outage er power reducden.

not 2 reportsble cerurrence was involved.) If the outage or power reducnon wu! not result in a reports:le oc:urrence.

NUSIBER. Th:s : iumn should indi::te the sequential num-the positive mdi:stion of dis lack of correist:en should :e ter assigned to each shutdown or stgruncant reduction m power noted as not appli::bie (NiA).

for m2t e:.iendar year. When a shutdown or s:gmdcant power SYSTE31 CODE. The system in which the outage or power reduction begins in one report pened.and ends m 2nother.

reduenon on2msted douo. be noted :v de two dq.:t ecce at.

n an entrv should be made for born report penods to be sure cxmott G Instruencns for Preparanon of Data cntry sneets di shutdowns or sipideant power reduenons are reported.

for Licensee Event Re:on (LER) r..

(NL. REG.v,161).

ue (rtt:12 unit has 2:aleved its.:rti power jeneration. no ".um-u ber should be assiped to e2:n entry.

Systems dat do not fit 3ry existag Ode should Oe des:p2 ted XX. The :cce ZZ should be used for 2ose events where DATE. This column should mdic2te the date of de start 2 system is not appli:2mie.

of each shutdown or siptd: ant power reducnon. Repert as year. month. and day. Aupst 14.10 7 would be reported COSIPONENT CODE. Seie:t de most apptcpnate ecmpanent as 770514 When a shutdown or npine:nt power reducten from Ex ubit I. Instru: dens for Preparzuen of Data Entr3 begms in ene report pened and ends m :noder. an entry should Sheets for Licensee Event Report (LER) File @CREG.016I).

be made for both report pencds to be sure all shutdowns usmg de followmg :ntiena:

or ::gmscant power reducdons are reported.

TYPE. Use "F" or "S" to indicate e:ther "For:ed" or " Sche-Juled." respe:uvely, for each shutdown or sipin:2nt power 3.

If not a component fa11cre. use de re:sted ;;m:cnent.

reducnon. Forced shutdowns indude dose required to be e.g.. wrong valve operated throup errort :ist valve as imtisted by no later than the weekend following discovery comconent.

of an aff. normal condinon. It is recogm:ed that some judg.

ment ts required in :stegonz:ng shutdowns in t!us way. In C.

If a chain of failures ce:urs. the nrst :cmponent to mai.

general. 2 for:ed snutdown is one that would not have been funcdon should be listed. The secuence cievents, melud.

completed in the absence of de :endinon for which :orre:nve ing the other : mponents which fail. could be des:nbed acnon was taken.

under the Cause sad Corre:nve Acton to Prevent Recur.

rence colunm.

DURATION. Self-explanatory. When a shutdown extends Comeonents dat do not St any ex:stmg :cde sn.outd.:e de-beyond the end of 2 report penad. count only the time to de

,jg,,ted XXXXXX. The code 777777 should be used for end or de report penod and =ici un the ensuing down time events where a component.aesignanon is not appliesele.

m the foiIowmg report penods. Report duracon of outages rounded to tne nearest tenth of an hour to fac:litste summanen.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-6ne sum of tt:e total outage hours pius the hours the geners-RENCE. Use de :clumn m a narranve fash:on to ampitfy or tor was on ime should equal the arcss hours ;n the reportmg ex:iam t,e circumstances of the shutdown orpower recuenen.

E'" "-

The ;olumn should mclude tne syt::Sc :2use for each snut.

down or sizmde:nt power reduencrt 2nd the immediate anc REASON. Cate2onze bs.etter demnadan a accordance centemetated Iona term corteente scucn taxen. if 3: preen-with the table a:peatmg on tne report form. If :steg0rv H a.

2te. an:s cotumn should also be use. tor a de:cnetien of tne must 5e used.suspiy bnef eurnments.

mater safety related corre:nve mamtenance per:ormec.2unna StETHOD OF SHLTTING DOWN THE REACTOR CR d' # "'*I' d' E * *' "d2'U " **I'di".*

d#""0C "C " d (

* #U""

pad 2;gty and a repon at any smate fmase et REDUCING POWER. C4:egonze ry numner denznsuun r:ctosenytty or smgle radisuon ex:csure spee:nestly assee:.

1% e that thts differs trom the Edison E:ectne Insutute atec with de out:ge which accounts for more t.tn 10 per;ent tEEli dedrunons of " Forced P:rud Outsp" 2nc "Sene-ci de 2110*20ic annual v2iues-cu.ed P:rual Outap." For these tema. eel uses a shange at For long textual re: orts eentmue narrative on se:2r:te pa:er

.t0 SIW 25 the creak, pomt. For larger puwer resetors.30 StW and reteren.e the shutcown or power reduonvn roi n>

.s too small a.hange to wanant espunanon.

narranve.

)

lot**

j

-m w

e.n

.O e

m.

-m

Docket No.: 50-316

+

Unit Name:

D. C. Cook Unit 2 Cmpleted By:

R. S. Lease

+

Telephone:

(616) 465-5901 Date: 5/9/83 Page:

1 of 2 MONTHLY OPEPATING ACI'IVITIES - APRIL 1983 Highlights:

The Unit entered the reporting period operating at 100% p wer and remained in service for the entire period. There were eight minor load reductions.

None of the reductions were below 80% pcwr.

Total electrical generation was 812,360 M H.

Sunmary:

4/2/83 Unit power was reduced to 95% for testing of turbine valves. Following the valve testing, unit loading was maintained at the 95% level due to low dmand on the power grid. Unit loading was returned to 100% power the following day. Total time below 100% power was 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

4/5/83 Unit power reduction was initiated at 1359 hours0.0157 days 0.378 hours 0.00225 weeks 5.170995e-4 months . Train "A" of the Solid State Protection System (SSPS) of Reactor Protection had been bypassed for 50 minutes for surveillance testing an1 it was evident that the testing would continue for greater than the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months that is allowed by Technical Specifications. The surveillance testing had identified a problem with one of the Solid State Boards. This required board replacment and retesting. The surveillance testing was empleted and Train "A" of the SSPS was returned to normal service at 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months .

Unit loading had been reduced to 99% at this time. Power vas returned to 100% by 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months .

Steam Jet Air Ejector Radiation Monitor (R-15) was inoperable for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period while the detector was replaced.

4/8/83 Unit power was reduced to 95% for testing of turbine valves. Total time below 100% was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4/14/83 The Control Rocm Cable Vault "Halon" Fire Suppressicn System was declared inoperable at 1707 hours0.0198 days 0.474 hours 0.00282 weeks 6.495135e-4 months when actual test of the system revealed the inability to maintain the proper "Halon" concentration.

The Steam Heating coils of the Main Turbine Reheaters were removed frcm service at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months . A coil leak was suspected in the left Southeast bundle and this was later confirmed by testing.

Unit power reduction to 95% was initiated at 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months . This load reduction was intended to allow testing of turbine valves and the return of the Reheater Coils to service. The upper limit switch of the Operating Device (Governor) would not clear at the 95% level and power was further reduced to 93% where it still would not clear. The opening of this switch was required to allow the Operating Device to respond to valve testing.

The limit switch was disconnected and Unit loading was returned to 100%

without either testing turbine valves or returning the Reheater Coils to service. Total time below 100% was 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

0001.0.0

Docket No.: 50-316 Unit Name:

D. C. Cook Unit 2 Cmpleted By:

R. S. Iear,e

+

Telephone:

(616) 465-5901 Date: 5/9/83 Page: 2 of 2 4/16/83 Unit loading was again reduced to 95% for the purpose of testing turbine valves and returning the Reheater Coils to service, which were successfully acmplished. Total time belm 100% was 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

The Reheater Coil configuration remained as six coils in operation. In the left hand Reheater the Southwest Coil had been out of service only because the Southwest coil in the right hand Reheater coil was inoperable.

'Ihis unused (Southwest) coil was placed in service rather than the Southeast coil where tube failure had been detected.

4/22/83 Unit power was reduced to 98% for testing of turbine valves. Total time below 100% was 4-1/3 hours. Reduction of power to test turbine valves was not necessary since the upper limit switch of the Operating Device had been made inoperable 3/16/83 but this reduction was taken as a precautionary measure. Turbine valves have been successfully tested at full power since this time.

4/24/83 The station was placed on Eastern Daylight Savings Time at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

All future times will be in reference to this.

4/26/83 Unit pmer was reduced to 80% over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp starting at 1657 hours0.0192 days 0.46 hours 0.00274 weeks 6.304885e-4 months .

'Ihe "A" string of high pressure feedwater heaters were rmoved frm service due to suspected tube to shell leakage in the 5-A Heater. This leakage was confirmed and the heaters rerrained out of service for repait. Reactor power was returned to 100% over a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months rar:p starting at 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months .

Electrical output was 30 FW 1ess than normal due to the less efficient operation with only one set of high pressure feedwater heaters in service.

4/30/83 Unit loading was reduced to 98% to return the "A" set of high pressure feedwater heaters to service following the repair of tube to shell leaks.

Total time below 100% was 4k hours.

Main condenser halfs were out of service, one half hour at a time, for a total of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months during the reparting period for identification and repair of circulating water leaks.

0002.0.0 t.

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 5-11-83 COMPLETED BY B. A. Svensson TELEP110NE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED HAINTENANCE APRIL, 1983 M-1 The West CCW pump suction sample isolation valve, CCW-199, was leaking by.

Replaced the valve.

M-2 The reciprocating charging pump primary water make-up valve, PW-277, was leaking by.

Replaced the valve diaphragm.

C&I-l Control rod stationary gripper coil phase 3-30 amp power fuse blew for no apparent reason, bringing in an " urgent failure" alarm. The fuse was replaced and the system was functionally tested.

C&I-2 Steam generator No. 4 power-operated relief valve, MRV-243, had an air leak on its control air solenoid. The relays and boosters for MRV-243 were rebuilt. Proper operation was then verified by stroking the valve.

C&I-3 While testing solid state protection system train "A" logic, problems were identified on points 2 and 5, logic switch "A",

and on permissives switch positions 10 and 11.

Troubleshooting revealed a defective universal logic printed circuit card in position A-304.

Af ter replacing the card, logic, permissives and memories were satisfactorily retested.

C&I-4 Reactor coolant loop No. 2 cold leg resistance-temperature de-tector (RTD) failed high. A resistor was substituted for.the failed RTD, in instrument rack No. 6, to simulate a temperature of 100 F.

This-low simulated temperature at the saturation meter input will prevent the high selector from selecting loop No. 2 cold leg input for T saturation computations.

C&I-5 Pressurizer pressure indication channels II and III had a difference in readings of 20 psi, which was an administration notification limit. After recalibration of indication channels I, II and IV, readings returned to normal.

C&I-6 Lower containment airborne radiation monitors, ERS-2300 and ERS-2400 AC power box, were rewired to conform with AEP elec-trical drawings.

I.. '

8 p %

N X,, IN0 LANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgrran, Michigan 49106 (616) 46M901 May 11, 1983 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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of April, 1983 is submitted.

Sincerely, u/4c%'vlw W. G. Smith, Plant Manager WGS:ab Attachments cc:

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

[ip

ML20076H060

Text

Navigation menu

Search