Text

Monthly Operating Rept for Apr 1980.Includes Revised Sheets for Feb & Mar Monthly Operating Repts,Correcting Item 16 Re Gross Thermal Energy Generated
	ML17318A761
Person / Time
Site:	Cook
Issue date:	05/02/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17318A760	List: ML17318A759; ML17318A761;
References
	NUDOCS 8005200620
	Download: ML17318A761 (12)
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8 ooeaoo o so G?iRATiYG STATUS OPERATIC DATARiPORT

'I DOCK:"TNP.

DATi CO.iIPLiT=

TiLiPHOy:- ~~ill1 ett

- eoi Donald C.

Cook

l. Unit ilatnec

2. Reportino

?eood'.

Licensed The....al Power (M)Vc)t

4. N tneplate Racing (Grass,'iDVe):

S. Desi'le"mM Racing (Nec %1Ne):

6. mfa"rtnam Dependabl= Capacity (Gross MYe)c

7. 5faxitnurn Den ndabl Capac:c (zf c MWe):

1980 3391 1133 1082 Iiotas S. IfCnanges Occur in Capac c r Rat'".y, (!teens Yvwbe S Throu~~% 7) Sine" Last R='por:. Give Reasons:

9. Power L vei To Phil Resc.'cc~, IfAny (.'fec ADVe):

10. Reasons For R seicciora, IfAny:

This Month Yr:to-Dat=

Cumulative ll. Hou=s In Reporting Period IZ. Number Of Haul Re"ctor ufas C;:cial IS. Re"ctor Reserve Shutdovvn Ho--.

14. Hours Generator On-Line IS. Uric Raerve Shutdown Hove

16. Gross Thecal ine~y Gene.

ted (lfNH)

17. Gross ilec ical ineroy Generac " {i'iWH)

IS. Yec ilectri 1

ser~y Gener" " (.'OVH)

19. Unit Service Factor

20. Ur:it Avaiiabili~ Factor I. Unit Caoacity."actar (Usia~ ~!DC Yet) 2". Urit Caoacity Factor (Using DiR 4et)

"3. Unit Forc=d Ou.'a~e Rate

"'. Shvtdowrs Scheduled 0'er Next 6 ~ion'.hs 719 707.7 0

2,903 2)4 0

0

, 54,3 9

0

7,523,166

98. 1

81. 0 81.

95.1 1.9

!Type. D"te. and Dr=ation of i"ch):

2.4

~77 7

~2 752,408 2 389 325 20 423 0

12,854.2 0

39,747 546 12 156 737

71. 7 71.7 11.8 "5 lfSa

. DownAt ind Of Re-ort P.riod. istirnated 0 t of Startvo:

, 'S.

Units in Test Status l?rior to Co.-..,.ercial Ope.=tionn Fore-.st Achieved IYITIAL CR!TICALITY liiiTlAL i'CTRlCITY CO.'i.'liRCIA'piRAt iOX Includes correction of February 1980 report - 43,769 NWHT.

i >js: )

AVihE DAILY UNIT PONER LEVEL

~

DOCKET NO."

"5'0-316 UNIT 2

DATE 5-1-80 COMPLETED SY W. T.

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

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 10 12 13 15 16 1092 1085 1090 1090 1091 1089 1086 1087 1083 756 1079 1084=

1088 1090 1085 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1084 235 1079 1079 1079 1082 INSTRUCTIONS On this format list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

OPEK<TLXG DATAREPORT DOCK:"TiO.

CO~fPLK~""D "- Y TEL:"PHOY=

~50-6

~

OP os lgr S

'TQS Oonatd C.

Cook o<<~

Pe-od:

Februar S.-Lic nsed The~J Pawer (id'IYt)t

4. Namepfate R tf.".~ (Gross <iOYe)!

S. Desi'ie"mM R":i'YetbiNe):

6. !tf~mutn Dependabl=.Capaci~

(Gross bfNe)t

7. Nfaxir<<um Dependabf Capac ty,fib t bfNe}:

1980 3391 33 1118

- 1082 Notes S. IfChmges Occur in Capa=:.y R t'".y, (Items 4vaber 3 Through 7) Sine" I st Repor.. Give Reuons:

9. Pov'er Level. To Nhi"'t Res '~~, I~.Any(.iet IINe):

IO. Reasons For Rest-..c"ore,1 Any:

This ~fonth Yr:to-Dat=

Cu

-'"tnIe 1S 16.

17.

10 Hou=s ln Report ~g Pe-..od'u;..ber Oi Hove Reactor Was C.":.~

Re-"c!Or Reserve'e Sntttdo'iTaT Iov<<s Hours Ge..e. tor On-Lw Urdt Rw~e Shutdown Ho -~

%9 Gross Thermal Enemy Gene.=t d,{MNH)

Gross Elec"~oaf ~ue~y Genera!~ (lffYH)

Net Electnc"I Energy Gener t d {If'IYH)

Unit Service Factor VritAvailabifiiuFactor Unit Capacity.-actor {Using L~IDC Net)

Unit Forced Ou!ag Rat" Shutdov <<s Sc'.".eduled 0'er Yext o ~fonths (Type.

696 680. 6 670. 3 165 634 714 670

'89,185

96. 3

96. 3 1440 1001.4 921. 0 0

420 863 137 64.0 64.0 2.7 3.7 Date. and Dv=ation of mchf!

18,960 12,081. 3 ll 422:9 0

10 630 549

69. 1

62. 9 1.0

".S. lf'Shvt Do-"n At End Of Re-ort Perioo. Es!iinated 0 te ofStartup!

~

. "5. Units ln Test S;a:us Iprior to Co......ercialOp.tionI:

Force"st

/

=

--IZIT:A. X TiYALITY fbiAXIALE'CTRIClTY CO: I ~fERCIAi. OPERATION

Correction NWHT - 43,769 ILir7: I

OPERATIC DATARcoORT DOCy=T qO 50-316 D iE M~O COiIPL TED;"Y ~~1ett TELcp~OiE ~%5='i901 OPE<ZTING STATUS Donald C.- Cook-

<<~, -,.'.

March

3. Licks&The....alPoorer (51St) t

4. Narneplate R &g (Gtoss iiOV=}t

5. Desi@. EIe"mM Ratin (Net ND'te)t

6. hI "'mvntt Dependabl= Capacity.-(Gross.MYr'e) t

7. ifaximntnD p=adab!

Cap cit (V tMNe)t S. IfChm~es Oc='r in Capa"'ty R r.~ (Items Number 1980 3391 133 Notes 1118 1082 3 Throv~~') Sine" Last Repor-.. Give Reasons:

9.

P ov'ec Levd To %hi 'z R~ct~jiAny p'et ~D>'e}:

10. R~ons For Rest;.at!or>.Lf A y:

This bionth Yr.-to-Dat.

Cninnlative IZ. Yv=..ber Of!Iona Reactor Vr' C;: M 13 Re ctor Reserve Shgtdovtil Hov s

14. Ho~ Gererator On-Line Io. U."~t R~rve Shotdown!:o m

16. Gross Thecal Enemy Cere. t~'ME/H)-

13.

i%et Bectrical Ene:gy Gen. '. (.'I'iVH)

20. Urit Avaihbili-.y Factor "1. Unit C"oacity '"ctor (Usi".~ i~!L~ Yet) 2". Unit Caoacity Factor (Using DER >Net)

23. Unit Forced Ovta~e,Rat

4. Shtttdo-'vs Scnedvled O'r Netct 6 lonths (Type.

728. 4 0

726. 1 0

$418, 99 801;060

773, 80 1 729.8 0

~

1 647.1 0

5,168.837 1,698,480

75. 4

69. 3

68. 1 2.6 97..6

96. 1 94.5 2.4 Date. and Dv=ation of Each I:

12 809.7 0

12 149 0

~~37 393 217 11,852,890 11,404,329

70. 5 64.5

63. 4

12. 3 "S. If Sn

. Do -n At End Of Repor: period. Es!irnated Date of Startnp:

5. Units In Test Statvs (Prior to Ccn-...etc!a! Ope-.tionI:

I'orc"st Achieved il. Y.

IYITIAL ELECT? CECITY CO:Iia RCIA1 OPERATION

Includes correction of February 1980 report - 43,769 NWHT Insgi)

UNITSIIUTDONNS AND POPOVER REDUCTIONS REPORT hlONTII Ap DOCKET NO.

COhlPLETED DY B.A. Svensson

~51 6 N().

Dale PI cjJ

~)r

~

Q Ot Q

~ Ii) g O

Licenscc Event Report rr OJ V

~A CCl~

OC 2 ~

Cr Cause h. Corrcctivc Acth)o to PrcvcnI Recurrence 75 76 800411 800419 F

0 A

F 136 A

N.A.

CH HECFUN CA VALVOP Reactor power reduced to 585 to re-move the west main feed pump from service due to faulty pump-turbine coupling.

Repair completed and re-actor power returne'd to 1005 800412.

Reactor/Turbine trip due to steam flop/feedwater flow mismatch coinci-dent with low level in No.

4 steam-generator.

Low feedwater flow and steam generator level was due to problems with No. 4 steam generator feedwater regulating valve, when attempting to recover from an auto-matic isolation of moisture separator

.-reheater coil bundles.

The Unit was returned to service the same day.

100$ reactor power reached 800420.

I.: For<<cd S: Sehed<<lcd (9177)

RCJson:

A-frluipmcnt Failure (fxplaio)

D.Maintenance or Test C.Rcfucliolt D-RCI,ulatory Restriction I!.Operator 'I'rainh)II& License Iixaolination F-Administrative G.Oper J IlooJI Error (I)xplahl)

I I.Other (EXPIJhl) hlethod:

I Manual 2.Manual Scfaol.

3-Autoolatie Scraol.

4-Other (Explaio)

Exhlblt G - Instructions for Preparation ol'Data I!otry Shccts lor Licensee I'vent Rcport (LER) flic(NURI:.G-016I )

5 L'xhibit I - Salnc Source

UNITSHUTDOWNS AND POWER R CTIONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source of explan-ation of significant dips in average power levels.

Each signi ~

ficant reduction in power level (greater than 20/o reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completelyl.

For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.

The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

NUMBER.

This column should indicate the sequential num.

ber assigned to each shutdown or significant reduction in power for that calendar year.

When a shutdown or significant power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure'l shutdowns or significant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber shouid be assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or significant power reduction.

Report as year. month. and day.

August i4. 1977 would be reported as 770814.

When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiricant power reducuons are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In general.

a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Self<xplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end ot the report period and pick up the ensuing down time in the following report periods.

Report duratidn of outages rounded to the nearest tenth ofan hour to facilitate summation.

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

tor was on line should equal the gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing un the report form. Ifcategory H must be used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that this differs irom the Edison Ele tric Institute tEEI) deimitions of -Forced Partial Outage" and

-Sche-duled Partial Outage."

For these tern>>. EEI uses a change oi'0

~IW as the break point.

For larger power reactors.30 WIW is trio small a change to warrant <<xplanation.

in accordance with the table appearing on the report form.

Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT.

Reference the applicable reportable occurrence pertaining to the outage or power reduction.

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to asc rtain whether or not a reportable occurrence was involved.) Ifthe outage or power reduction will not result in a reportable occurrence.

the positive indication of this lack of correlation should be noted as not applicable (N/A).

SYSTE!>>I CODE.

The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G -Jnstructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

COMPONENT CODE. Select the most appropriate component from Exhibit I

~ Insiructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

using the following critieria:

A. Ifa component failed, use the component directly involved.

B.

If not a component failure, use the related component:

e.g.

~ wrong valve'operated through error: list valve as component.

C.

If a chain of failures occurs, the first component to mal-function should be listed. The sequence of events. includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.

Components that do not fit any existing code should be de.

signated XXXXXX. The code ZZZZZZ.should be. used for events where a

component designation is not, applicable.

CAUSE"'&'ORRECTIVE 'ACTION TO 'PREVENT-RECUR-RENCE.

Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken. ifappropri ~

ate.

This column should also be used for a description of the major safety. related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release ot radioactivity or single radiation exposure spe<<itically associ-ated with the outage which accounts for more than 10 percent ol the allowable annual values.

For long textual reports continue narrative on separate paper and ret'<<ren<<e the shutdown or power reduction foi thi>>

IlarfJtlve.

Docke~.:

Unit~e:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 C.

E. Murphy (616) 465-5901 May 6, 1980 1 of i3) t10NTHLY OPERATING EXPERIENCES -- APRIL, 1980 a ~

Hi hl i hts The Unit operated at 100/ power the entire reporting period except as detailed in the Summary.

There was one outage of the Reactor and Turbine Generator Unit during the reporting period.

This is also detailed in the Summary.

Total electrical generation for the month was, 801,060 Mwh.

~Summar 4/1/80

-- The Hest Centrifugal Charging Pump was inoperable for a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period to renew the gasket on the Suction Strainer Connection.

The Diesel Fire Pump was removed from service at 1102 to replace a radiator hose.

This was returned to service at 0920 on 4/3/80.

The North half of "A" Condenser was out of service for a 7.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for checking of tube leaks.

4/3/80

-- Radiation Monitor R-11 and R-12 were inoperable for a

6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period for replacement of the sample pump.

4/6/80

-- A High Minding Temperature Alarm was received on 9 3 of the Hain Transformer at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months .

This temper-ature was carefully monitored with the highest indica-tion being 109oC.

This has been checked out and is believed to be a faulty instrument.

The Alarm is cleared at this time.

4/8/80

-- The North half of "B" Condenser was out of service for a

6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period, for checking of tube leaks.

4/10/80 -- The South half of "A" Condenser was out of service for a

10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period for tube leak check.

Reserve Power Source Breaker 12-AB was opened at 1819 hours0.0211 days 0.505 hours 0.00301 weeks 6.921295e-4 months .

This was to make repairs to the terminations of one of the underground cables.

This power source was returned to normal at 0123 hours0.00142 days 0.0342 hours 2.03373e-4 weeks 4.68015e-5 months on 4/11/80.

(i,

DocketjQp.:

Unit~e:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit b'2 C.

E. Murphy (616) 465-5901 Hay 6, 1980 2 ofx3I 4/11/80 At 0215, a power reduction was initiated when excessive wear was detected on the West Hain Feed Pump Coupling.

Power was leveled,off. at 58%.by 0303 and the West Hain Feed Pump'emoved from se'rvice.

During the power reduction the Axial Flux was out of the target band for a period of 18 minutes.

The Unit power level was returned to 65% by 0445.

The West'ain Feed Pump was returned to service at 1822 and the Unit loaded to 100% power at 0112 on 4/12/80.

ARV-ll, 'Hain steam to the East Feed Pump Turbine Reducing Valve, failed open at 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months .

Local Manual Control was required while repairs were made.

ARV-ll was returned to service at 1050.

4/15/80 4/16/80 4/19/80 4/21/80 4/24/80 The West Centrifugal Charging Pump was out of service for a 5.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period, while repairs were made to a Component Cooling Water line.

The Blowdown Radiation Monitor R-19 was inoperable for a 9.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for repairs to a Safety Valve.

The West Centrifugal Charging Pump was out of service for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for breaker maintenance.

At 0110 the Unit tripped from a steam fl'ow/feed flow mismatch coincident with a low Steam Generator level on No.

4 Steam Generator.

This was the result of a transient initiated by the isolation of the North Reheater Coils from a high level in the North Coil Drain Tank.

The North Heater Drain Pump then tripped and would not restart.

The No.

4 Steam Generator level control was placed in manual due to it's sticking action.

The Valve traveled too far in the closed direc-tion and could not be reopened in time to prever'rt the trip.

The Reactor was critical at 1246, and the Generator paralleled at 1458.

The Unit was loaded to 100%

by 0146 on 4/20/80.

Containment Radiation Monitors R-11 and R-12 were inoperable for 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months to repair the paper drive.

"A" North:iCondenser half was removed from service for 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to check for leakage.

The No.

3 Boric Acid Transfer Pump was removed from service at 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months , for maintenance to repair a bearing.

This pump was returned to,service at 0940 on 4/26/80.

Docket.:

Unit HPiiie:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82 R.

S.

Lease (616) 465-5901 May 6, 1980 30f 3 4/25/80 -- Condensers removed from service for leak testing and repairs were as follows:

"B" North for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months "B" South for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months "A" South for 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months "A" North for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months "C" North for 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months "C" South for 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months The Power operated Relief Valve for 83 Steam Gen-erator was out of service for a period of 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to repair steam leak.

4/30/80 -- R-25 The Air Particulate Detector for. the stack Monitor was inoperable for a period of 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

(

j

~

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 ook Unit No.

2 5-13-80 B. A. Svensson 616 465-5901 1 Qf MAJOR SAFETY-RELATED MAINTENANCE APRIL, 1980 M-1 CSI-1 CSI-2 CSI-3 CSI-4 Sample pump for R-11 and R-12 would not maintain correct flow rate.

Replaced sample pump and unit functioned properly.

Sample pump for R-ll and R-12 would not provide adequate flow.

Re-placed pump with a rebuilt pump.

No.

3 steam generator power operated relief valve, MRV-233, had a

packing leak.

Repacked valve and verified proper operation.

During performance of surveillance testing for NUREG 0578, mechanical seal leakage was noted from the west centrifugal charging pump.

Re-placed the pump outboard mechanical seal.

Also replaced one set of thrust shoes and changed oil.

Verified proper pump operation.

The No.

3 boric acid transfer pump was making noise.

Replaced the bearings',', mechanical seal

'and gaskets.

Verified proper pump opera-

tion.

18 The "Loop 1

RTD Bypass Manifold Flow Low" alarm was received in the control room.

The circuit to the instrument in containment indicated a ground condition.

Water was found. dripping",on the cables.

Actual flow was verified to be greater than the 'alarm set point.

Radiation Monitoring System Channel R-19, steam generator blowdown

monitor, was producing sporadic indications and tripping the blowdown system.

Connectors were replaced on the power cable to the terminal board.

The channel was energized and normal operation was verified'he hand-auto station for FRV-240, feedwater regulating valve to steam generator No. 4, operated in fast response mode (manual) with the manual control in the slow response position.

The contacts on the manual control switch required cleaning.

An operational test of the manual control feature was performed.

Steam Generator No. 1, protection channel steam line pressure PT-514 (MPP-210), indicated a higher pressure than adjacent channels.

A calibration was performed on PT-514.

The as-found data indicated a

maximum error of 2.254.

The transmitter was recalibrated to a maximum error of 0.125$

and returned to service.

~

If Y

I f,

f

ML17318A761

Text

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