ML20050B403

Monthly Operating Rept for Jan 1982

ML20050B403
Person / Time
Site:	Cook
Issue date:	01/31/1982
From:	Might A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20050B399	List: ML20050B398 ML20050B403
References
NUDOCS 8204050294
Download: ML20050B403 (8)

Text

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CPERACiG DATA RE?CRT DCC'GT NC. 5-315 1_ u _ p 9 On.--e.

CO.\\:?L.~. TIC EY a ***

616-4 6-6901 0

TELE?HCNg C?mT!NG S~ATUS No::s Donald C. Cook Plant 1 g, g,; 33m.

~

Januarv. 1907

2. Repo4 ?-dod:

3250

3. U:=r.sedT' ---l?wer(31W:):

1089

4. Nan:eolate R :i=;(Cro:s 5tWe):

1054

3. Desip Eie==d=1 R=in; {Nec 1DVe):

1080

6. 5t +um Dependshls C:ys=i:7 (Cross 51We):

IOd4

7. 'in-- -m De;

'"! -t $st 3DVe):

S. If r"'- ~;es Oc=:in C:pci:7 R :.;s (1::=s Numb : 3 Threu;h 7) Sine: Lu: R:per:. Give R: sons:

9. Power L.ve!To W $ Res= --3. If Any (N:: 3twe):

10. R== sons For R" dans.If.L.y:

This Sionth Y:ao. Cat Cu==I::ive 744 744 62,112

11. Hours != R:po::i=; Peded 503.2 503.2 40.776.4

12. Nu=her Cf Hou:s ac=ce W:s C:f:i=I 0

0 463

13. Rec:or Reserve Shutdown Ec*:.-s 496.8 496.8 45,719.0

14. Hocrs Gene =ter ca.Un, 0

0 121

15. U:.i: R seve She down Eccs 1,569.517 1.569.517 131.932.706

16. Cross Thd E==::y Cent:::ed (3twH) 494.400 D25,490 43.407.270

17. Gross Ele =:i=1 Ese;y Cee_::: d IJ.tWH) 507.?43 507.243 41.747.921

13. Net E!e==f J E== ;y Gene =::d t.'.tWE) 66.R 66.R 76.3 l

19. U=it Servi = f:::or 66.8 66.8

/6.3 l

20. Uni: Ar..il: hie:7 :c:or F

65 1 65.J ob.o

22. Uc!:C:pci:f F::::r(Usi::: SIDC Nec) 64.7 64.7 65.0 f

22. C:i: Cae: city F:::or (Usin; DER Net 32.4 32 4 7.1 l

23. Uni: Fore:d Cu::ge R:te l

24. Sh::dowv.sSched=l:d OverLc 5 Ston:!:s (Type.D:te.: d Oc=:fon o(Y: chi:

3/1/82

• 3. If Sh:: Down At End Of Report ?:riod. Esti==:ed D:te o(St:-:to:

.25. Units la Tes: S;:: s iP::or to Ce==eni:1 Open: ion 1:

Fore =st Ac.hieved INITIA:. CRIT:CA LITY

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INI7IA L I.ICTR:C;-~Y CO?.it.:I?.C:A. O?Ey..A 7:CN l'8/771 8204050294 820212 PDR ADOCK 05000315 R

PDR

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

DATE January 31, 1982 CCMPLETED BY A. Might TELEPHONE 616-465-5901 MONTH January, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (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 fannat list the average daily unit pcwer level in MWe-Net for each day in the reporting month. Ccmoute to the nearest whole megawatt.

DOCKET NO. 50-315 UNITS!!UIDOWNS AND POWER REDUCTIONS UNIINAME D.C. Cook - Unit 1 DATE 2-12-82 January, 1982 COMPLElED HY B.A. Svensson HEPORT MONT.I 1El.EP110NE (616) 465-5901 PAGE 1 of I "t.

$2

1. ice:Isee h*t, Causc & Caisseclive No.

Date g

3g

)y$

livent

[?

p Action to g'

fE s

j;g g

tep.n 4 mo Peeveni Recuirence i-177 811229 F

229.9 A

1 81-062/03L-0 CB VALVEX The unit was shut down to repair RCS Cont'd leak. The unit was kept in cold shutdown to complete work inside con-tainment on NUREG-0737 items. The unit was returned to service on 820110 and reached 100% reactor power on 820111.

178 820130 F

0 B

4 N.A.

ZZ 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.

179 820131 F

17.3 A

3 N.A.

ZZ ZZZZZZ Unit tripped from high turbine vibra-tion.

Inspection revealed a blade failure 'n the " turbine end" first stage.

.ne unit remained out of ser-vice at the end of the month. A five week outage is estimated.

I 2

3 4

I; I mcet!

Heason:

Metinal:

Exhibit G -Instsuctiims S: Sc heilulcil A. Equipment 1:ailuie(Explain) l-Manual for Psepasation of Data li Mainienance of Test

2. Manual Scram.

Entry Sheets Im 1.icensee C. Refueling 3-Automatic Scram.

livent Repose (i.l:R) File INURIE D Regulainsy Restsiccion 4-Othes (Explain) 0161)

!!-Ope:ato l'eaining & License lixaminalian F-Athninisteative 5

G Operational Einor (limplaint lishibit 1 - Same Somce 19/17)

II Ol'ier (lixplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This repon should descr2e all plant shutdowns during the

n 2::ordance with the table appeartng on the report form.

report penod. In addition. it should be the source of explan-If:stegory 4 must be used. supply bnef comments, anon of st;mScant dipe m average power levels. Each umi-LICENSEE EVENT REPORT =. Referen:e the appli: sole fi: ant redu:non tn power level (greater than 20"e reduction m averase daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pe:tammg to the outage or power redu:non. Enter the Erst four parts (event year. sequential should be noted, even though the umt may not have been shut down completely!. For su:h reducuens in power level.

report number, oc:urrence code and report type) of the Sve the duration should be listed as zero, the method of reducuen pan designation as desenbed in Item 17 of Instrucuons for thould be listed as 4 (Other), and the Cause and Corre:nve Preparanon of Data Entry Sheets for Licensee Event Report Acuan to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). Tius informanon may not be Cause and Corre:uve Action to Prevent Recurrence column immediately evident for all such shutdowns. of course, smce should be used to provide any needed explanation to fully further mvesugation may be required to ascertam whether or desenbe the :ircumstances of the outage or power reduction.

not a reportaole oc:urrence was mvolvec.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indic:te the sequential num-the pouuve indication of this lack of correlanon should be bet asugned to each shutdown or agmncant reducuonin power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmil ant power SYSTD1 CODE. The system in which the outage,or power reduction beams m one report pened and ends m another.

an entry shoilld be made for both report periods to be sure reduction ongmated should be noted by the two digit code et.

11 shutdowns or sigmn ant 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).

ber should be assigned to es:h entry.

Systems that do not St any existing code should be Jeugna-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 signi5 cant power reduction. Report as year. month. and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component u 770314 When a shutdown or ugnificant power reduction from Exhibit ! Instru:tions for Preparation of Data Entr) begms m one report pened and ends m anc,ther, an entry should Sheets for Licensee Event Report (LER) File (NUREG 01611.

be made for both report penods to be sure all shutdowns usmg the following critiena:

or ugmficant power re'.uctions 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 be e.g.. wrong valve operated through erron list valve as initiated by no later than the weekend following discovery component.

of an off-normal condition. It is re:ognized that some judg-ment is required in :stegonzmg shutdowns in this way. In C.

If a cham of failures occurs. the first component to mai-general, a for:ed shutdown is one that would not have been function should be listed. The sequence of events.includ-completed in the absen:e of the condition for which corre:nve ing the other components which fail. should be desenbed action was taken.

under the Cause and Corrective Action to Prevent Recur-tence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any ex2stmg code should be de-beyond the end at a report penW eount only the time to the sted XXXXXX. The code 777777 should be used for end at the report penod and pick up the ensuing down time events where a component designation is not applicable.

m the following report penods. Report duranon of outages rounded to the nearest tenth of an hour 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 fashaon to ampiify 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-down at signincant power reduction and the immediate and REASOS,. Categonze by ietter deugnanon in accordance contemplated long term corre:tive scuan taken. if appropn-with the table appearmg on tne report form. If category H ate. This column should also be used for a desenotion of the must be used.suppiy bnet comments.

maior safety.related correcuve mamtenance performed dunna the autage or power reduction meluding an identification of METHOD OF SHUTTING DOhN THE REACTOR OR REDUCING POWER.

Categonze ey number dengnanon the ntteal p th aeuvity and a report at any smgle release of radioactmty or smgle radtation exposure speettically asscet.

1% e that this differs f rom the Edison E!eetne Insuture sted with the outage wtuch accounts for more than 10 percent t eel) denmttons of " Forced Parnal Outage" and " Sche.

of the allowable annual values.

culed Partial Outap.' For these term >. EE! uses a shange at For long textual reports contmue narrative on secar:te paper 30 MW as the breai pomt. For larger power reactors. 30 MW

nd reterense the shutdown or power reduonon foi mt.

s tiv small a shange to wanant esplanation.

narrative.

Nf3

Docket No.:

50-315 Unit Name:

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 Name:

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 turbine.

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 PAC:

1 of 2 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1982 M-1 Pressurizer power operated relief valve, NRV-152, 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. 1 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-ll The ESW 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 SAFETf-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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