ML20042A379

Monthly Operating Rept for Jan 1982

ML20042A379
Person / Time
Site:	Cook
Issue date:	01/31/1982
From:	Might A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20042A380	List: ML20042A379 ML20046D910
References
NUDOCS 8203230373
Download: ML20042A379 (7)

Text

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CPI 2.cc DATA RI?cF DCC CT NO. 5-315 DATI 1-U "

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CO.st?L.".n D SY a - **

7" ".SCNI 616-en5-6901 C?mTING 5 AT*.'S N028 Donald C. Cook Plant 1 3,gg,, %

Januarv. 100?

2. % ?rded:

12RO

3. UWThe==21Po=ar(MWt):

4. Namesiase Ras::(Cens: SUve): _ 1089 1054

5. Desip EW 2:.: int (Net SUV');

1080

4. *~ Dependahls Csysci:y (Cross 31We):

1044 T. 'faxmmn DW"Is C::rc=T(N'S 31W8):

8. If Chaarges Oc=:is Czysd:7 Rzt=gs (Ita=s Nu=bar 3 Through 7) Sines Las: Repor:. Give Reasons:

4

9. ?,.er La,d To W5 : 5 F-3. If Any (Net 31We):

10. Ra=sess For ? *-E Asy*

This Stonth Y.ao.Catr.

C =uk:ive 744 744 62,112

11. Eca:s !s Raper:ist eriod P

503.2 503.2 46,776.4

12. Nu=izer Cs Hou:s ?

ar Was C.u,

0 0

463

13. Sm-ar R=se.

• Sh::!ewn Hom 496.8 496.8 45.719.0

14. Hoczs Gace=:srca.Lhe 0

0 321

15. Ud: Kase:ve Shandown Hoc =s 1,569.517 1,569.517 131.932,706 Id. C<oss Th=--- I I=:::y Cent:.-:=d (MWM) 49E 400 04D,49U 43.407.270

17. CennElec=c:1Iseqy Cem=:md @tWH) 407.243 507.243 41,747,921

13. Ne: EW :-- ;y Cm -

' ptW,a.

66.8 66.8 76.3

19. Uni: Serri= E.scr 66.8 66.8 io.3

3. Ud Ar.ilsaE:y F:c:or 65.3 D5 3 06 0

22. Ud: C:=se 7 ::=r(Usi ; SirC Nec)

F 64.7 64.7 e5.0

. C:it Csoscity. :c:or (Using CIE Net 32.A 32 4 7.I

23. Usir.:or =d Cunge R:ce

24. Sh:dewr.s Schedded Cver Nen 6 Ston:hs (Type. 0:te. :::! Ot:=: ion of I:61:

3/1/82

• 3. If 5:=: Down At Isd Of ?.rport ?:riod. I:ti==:ed 3:te ot Star =o:

.25. L'aits la Tes: 5=::s IP=or to Ce==eni:10;r=rion :

Forr st Ac-ieved INITIA L C?.IT*CA LITY

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IN*TIAL ILIC7.: :W CO?.i:4IF.C;AL OPI?.A7'ON

'u,'*3 8203230373 820212 l

PDR ADOCK 05000315 R

PDR

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-315 UNIT 1

DATE January 31, 1982

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CCMPL:.TED SY A. Might TELEPHONE 616-465-5901 MONTH January, 1982 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVE!.

(MWE-Net)

(MWe-Net) 1 17 1051 2

18 1049 3

19 1050 4

20 1052 5

21 1053 6

22 1054 7

23 1039 8

24 1053 9

25 1051 10 118 25 1056 11 827 27 1056 12 1052 28 1055 13 1051 29 1054 14 1053 30 987 15 1048 31 294 16 1033 INSTRUCTIONS On this famat lis the average daily unit pcwer level in MWe-Net for each l

day in the rescrting month. Ccmcute to the nearest whole megawatt.

DOCKETNO. 50-315 IINIT SilUTI) OWNS AND FOWER REl>UCTIONS UNITNAME aD C. Cook - Unit I nATE 2-12-82 January, 1982 COMPLEiEn my B. A. Svensson REPORT MONTil TEl.ErtlONE (616) 465-5901 PAGE 1 of 1 "t.

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go.,

Cause A Consective N. i.

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g3 Actiene ess I

g' oE s"e jiji g Repius *

• a O Pievent Recusicace t-d I

177 811229 F

229.9 A

1 81-062/03L-0 CB VALVEX The unit was shut down to repair RCS f

Cont'd leak. The unit was kept in cold shutdown to complete work inside con-tainment on NUREG-0737 items. The j

unit was returned to service on 820110 and reached 100% reactor power on 820111.

178 820130 F

0 B

4 N.A.

Z1 ZZZZZZ Reactor power was reduced to 75% for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to permit re-pair of leak in the turbine control fluid system.

i 179 820131 F

17.3 A

3 N.A.

ZZ ZZZZZZ Unit tripped from high turbine vibra-E tion.

Inspection revealed a blade failure in the " turbine end" first stage. The unit remained out of ser-vice at the end of the month. A five week outage is estimated.

I 2

3 4

IE 170sced Reasim:

Methinl:

Eahible G. Insisucchms S: Silicilideil A 1:sguipmens I;ailme (I splain) 1 Manual Ios Psepasalism of Dasa 11 Mainicnance oi Tes!

2 Manual Sesans.

lintiy Sheces los liensee C-Rcfocling 3 Automatic Scsam.

livene Repius (l.l:RIl'ile INilRI G-D Regulatoiy !!csisicilos.

4-Other ( Emplain) 0161I l' Opesatos liaining & 1.icen>e lizandnailon 1; Ailndnisisasive 5

G Opesational 1:sios Ilimplain) lahihlt 1 - Same Sousce I'd/17) 11 Other (limplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Tha report should desenbe all plant shutdowns dunng the

n :::ordance with the table appearms on the report for:n.

oport penod. In addition. it should be the sour:: of explan.

If :stegory 4 must be used. supply bnef comments.

anon of ugmficant dips :n average power leveis. Eacn ugm.

fi: ant reducuon m power level (peater than 20", reduction LICENSEE EVENT REPORT =. Reference the appbc2ble m sverage daily power level for the preceding 24 houn) reportr,ble oc:urrence pertammg to the outage or power should be noted, even though the urut may not have been reduction. Enter the fint four parts (event year, sequent:al l

shut down completely. For such redu:uons in power level.

report number. oc:urrence code and report type) of the five tne duration snould be listed as zero, the method of reducuon part designation as desenbed in item 17 of Instrucuans for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for Licensee Event Repon Acuon to Prevent Recurrence column should explam. The (LER) File (NUREG.0161). Tha informauan may not be Cause and Correcuve Acuan to Prevent Recurrence column

mrnediately evident for ai! such shutdowns, of course, smce should be used to provide any needed explanation to fully further mvesugation may be required to ascertam whether or dos:nbe the :ircumstances of the outage or power reducuen.

not a reportable occurrence was invelved.) If the outage or power reducuon wtll not result in a reportable oc:urrence.

NUMBER. This column should indic:te the sequennal num.

the ponuve indication of this lack of :orrelauen should be oer ungned to each shutdown or ugntilcant reducuonin power noted as not applicable (N/A).

for that calendar year. When a shutdown or signuicant power reduction beg:ns in one report pened and ends m anotner.

SYSTEM CODE. The system in which the outage or power an entry should be made for both report penods to be sure reducuon ongmated should be noted oy the two dig:t eode ot.

ll shutdowns or sig:uil: ant power reduchons are reported.

Exnibit C Instrucuens for Preparst:en of Data Entry S,nects Until a unit has ach:eved its first power Seneration, no num.

for Licensee Event Report (LER) File (NUREC.0161).

ber snould be asugned to each entry.

Systems that do not fit any ex: sting code should be deugna.

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 reducuon. Report as year. month, and day. August 14.19M would be reported as 70314. When a shutdown or ugruficant power reducuan COMPONEAT CODE. Select the most appropnate :omponent from Ex!ubn !. Instrucuons for Preparanen of Data Entry begms m one report penod and enda m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161),

be made for both report penods to be sure all shutdowns using the followmg :ntiena:

or sigmficant power reducuens 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:

reducuon. Forced shutdowns include those required to b*

minated by no later than the weekend following discovery e.g., wrong valve operated through erron list valve as component.

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

ment is required m categonzmg shutdowns in this way. In C.

If a cham of failures occurs the first component to mai.

general. a forced shutdown is one that would not have been funcuen should be listed. The sequence of events.mciud.

completed in the ansence of the :endition for which correcuve ing the other components wh2:h fail. should be desenbed action was taken.

under the Cause and Correcuve Acuan to Prevent Recur.

rence column.

DURATION. Self.explana*.ory. When a shutdown extends beyond the end or a report penod. count only the ttme to the Comoonents that do not fit any existmg : ode should be de.

end or the report penod and pick up the ensumg down time ugna'ted.'CCXXXX. The :cde 777777 should be used for events where a comoonent designation is not spplicable.

m the following recort penods. Report duranon of outages ruunded to the nearest tenth of an hour to fac:litate summation.

The sum ut the total outage hours plus the hours the genera.

CAUSE & CORRECTIVE ACTION TO PREVEST RECUR.

tar was on line should equal the gross hours in the reportmg RENCE. Use the :clumn in a narranve fastuen to amoiify or penod.

explam the circumstances of the shutdown or power reducuen.

The column should include the socc:ile cause for each shut.

REASON. Categonze by :etter Jeugnation in accordance down or significant power reducten and the immediate and cith the table appearmg un the report form. If :stegory H centemolated lone term corre:nve acuen taken. if appropn.

This column'should also be used for a deser:ption of the are.

must be used. suppiy bnet comments.

maior safety-related correcuve mamtenance performed dunna METHOD OF SHUTTISG DOWN THE REACTOR OR the autane or power recucuan mc!uding an :denttilcation of REDUCING POWER.

Categonze bv numner denznauen the :=neal path acuvity and a teocrt of any untie reiease or radiosenvity or imgle tactanon exoosure saceuieally assco INote inat this datters trom tne edison Electne Insuture ated with the outage wtuch accounts for more than 10 percent (EE!) desimr.ons of " Forced Part:ai Outaae" anc "Sene.

Oi th* 211owaole annual values.

culed Part:al Outage ' For these terms. eel uses a hange at For long tex ual reports eonunue narrattve on secarate paper 10 MW as the breas pomt. For larger power reactors. 30 MW an.i referen e tne snutcown or power recu aon im un,

S f ois an1Jil J snante to Wartant C\\plarla!!oH.

n*2rrative.

Docket No.:

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

D. R. Campbell Telephone:

616-465-5901 Date:

February 8, 1982 Page:

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

The Unit entered the reporting period in Mode 5.

The Reactor Coolant System was drained to half loop in order to make repairs to NRV-164 (Pressur-izer Spray Valve).

NRV-164 had a ruptured bellows, this contributed to the valve blowing its stem packing.

This was the source of our greater than 1 GPM Reactor Coolant leak.

Repairs were made to NRV-164 and the Unit was paralleled to the grid at 1356 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.15958e-4 months <br /> on January 10, 1982.

The Unit reached 100% power at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on January 11, 1982.

On January 30, 1982 the power was reduced to 75%

to work on the main turbine EHC system.

On January 31, 1982 the main turbine tripped from high vibration.

The reactor was shutdown and cool-down started.

Turbine repairs were started.

Total electrical generation for the month was 525,490 MWH.

Summary:

1-06 Repairs to NRV-164 were completed and filling and venting of the Reactor Coolant System started at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br />.

1-08 Mode four was reached at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />.

1-09 Mode three was reached at 1644 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.25542e-4 months <br />.

1-10 Mode two was reached at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />.

The reactor was made critical at 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br />.

The Unit was paralleled at 1356 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.15958e-4 months <br />.

1-11 The Unit reached 100% reactor power at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

1-14 An unplanned gaseous release of about 3% of the Tech. Spec. limits occurred.

The cause of the release could not be determined, but it is believed to be associated with valving on the Unit 2 Volume Control Tank.

The event required a " Red Phone" call to the NRC.

Docket No.:

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

D. R. Campbell Telephone:

616-465-5901 Date:

February 8, 1982 Page:

2 of 2 Summary (Cont. ) :

1-15 Upper Containment air lock was inoperable for a short period to repair the door seal.

1-26 R-ll/12 Containment Sample pump failed and was out of service for about 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

1-30 The Unit power was reduced to 75% for four hours to repair a leak on the main turbine EHC system.

1-31 At 0641 hours0.00742 days <br />0.178 hours <br />0.00106 weeks <br />2.439005e-4 months <br /> the Unit tripped from 100% power due to high vibration on the main terbine.

At 1651 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.282055e-4 months <br /> the reactor was taken critical again to roll the main turbine.

At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> the turbine was rolled up to 800 RPM, then it was manually tripped after the vibration problems were confirmed.

1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> the reactor was shutdown and cooldown begun.

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 2-12-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1982 M-1 Pressurizer power operated relief valve, NRV-157., was leaking by.

Re-placed the plug, stem and seat.

Repacked and had the valve adjusted and tested.

M-2 Pressurizer power operated relief valve, NRV-151, was leaking by.

Re-placed all valve internals and had valve tested.

M-3 No. i S/G stop valve dump valve, MRV-211, was leaking by.

Replaced the valve seat, plug stem and gaskets.

Had valve tested.

M-4 Pressurizer PORV block valve, NM0-151, had a body-to-bonnet leak and had been sealed by Furmanite.

Replaced the disc and stem.

Repacked and reset limits.

Had the valve tested.

M-5 Pressurizer spray control' valve, NRV-164, had a packing leak.

The unit was shut down, cooled down, depressurized and drained to half loop.

The trim assembly bellows had ruptured and the packing subsequently blew out.

Replaced the trim assembly.

Replaced the cage spacer.

Repacked the valve and had it tested.

M-6 The stem of the reactor coolant filter drain valve, CS-381, was broken.

Replaced the valve bonnet assembly.

M-7 The auxiliary feedpump turbine governor valve linkage was binding.

Re-placed the valve stem and bonnet gasket, and the turbine was tested for operability.

M-8 The intake air filter screens for LAB emergency diesel would not move.

Cleaned oil reservoir, changed oil and replaced the shear pin.

M-9 No. 2 boric acid transfer pump discharge pressure was low.

Adjusted the impeller clearance and had the pump retested.

M-10 The west ESW pump discharge valve, WM0-702, was not closing completely.

Adjusted the limit switches of the motor operator and had the valve re-tested.

M-11 The CSW outlet pipe from the east CCW heat exchanger had several pinhole leaks.

Replaced a flange and 3' section of pipe.

Had necessary NDE performed and completed hydrostatic test.

DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 2-12-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1982 C&I-l The Control Rod Position Recorder indicated control Bank C at 220 steps during shutdown with the control rods fully inserted.

The low and low-low insertion limit alarms also were not received. The problem was traced to a BCD board in the. analog rod position indication cabinet.

The board was replaced and normal indication returned.

C&I-2 Loop No. 3 reactor coolant RTD T-Cold failed high.

The spare RTD was placed in service and the R/E module recalibrated to the spare RTD.

C&I-3 Radiation Monitoring. System Channels R-ll and R-12, containment air particulate and radio-gas monitors' sample pump tripped four times during a 30-minute period. The flow system of the monitors was tested.

The flow rate was found to be operating at 9.5 CFM. The flow rate was adjusted for 10CFM. A filter paper problem was identified during the work. The filter paper was changed.

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