ML17326A288

Monthly Operating Rept for Sept 1979

ML17326A288
Person / Time
Site:	Cook
Issue date:	10/02/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17326A287	List: ML17326A286 ML17326A288
References
NUDOCS 7910190376
Download: ML17326A288 (12)

Text

0 AVERAGE DAILYUNITPO>:-R LEVEL DOC).=T NO. >U-316

UNIT, 2

DAT"-

10-2-7 9 gOqIPLETED I)Y W.T. Gillett T:-

"=PHON:>>

616 465-5901 Se tember 1979 DAY AVERAGE DAILYPO4'ER LEVEL

(.'/INe-Ne:)

I 1033 1036 DAY AVERAGE DAILYPOKcR L V:"

(MNe Ne()

1048 9

IO 1036 1044 1042 1022 1048 1048 802 1043 1043 1042 1045 19

'/P 26 "S

l9 30 1046 1044 1048 1067 1066 54 1027 1053 10 993 514 l6 559 INSMcUCiiONS h-t<'i =~

2) ':2:;;

iV -22 i-j.V J;.!l "tÃe::e"e::...ii~l e.~e'. )Of -2=:l 22 l l" fe"i.-,l'."it:"..i/tll/l.Ci/Pl /-" t/i 0

I 2

'r ol oleo g )g

Oo"-84T'IG D 5 TA Rc POP T DOC~T YO.

DAT" COiIPLETFD ~Y TELE. HO~E

~50-W.T.Gillett

~16-465-5901 OPERATING STATUS

>. Report}a Period.

Se tember 3, Lt ensed Therma} Powc, (NINp)'3 1

4. Namep!"t P tirg (Gross,'4IWe):

1133

5. Design Elec~ca} Ra:ing (Yet 44INe):

1100 7.

4Iaximum Dcp ndabl Ca-a=:ty (h t YNe).

1082 Notes S. L'nanges Occu. in Capa"'ry Rat'"..".s (!t ms Number 3 Throuoh 7) Since I "st Repors. Give Reasons:

9. Power Level To Kiri 5t Res..!et~, IfAny (4%et MW ):

10. Reasons For Restzictior, 1f Any:

Thh Month Yr:to-Date Cumr.'"tiv 698. 7 5 394.0 0

0 693.1 5 319.1 0

0 723,270 5 680 510

~62 216 5.482 205 81.2

96. 3

96. 3 76.1 88.0 18.8 Du:ation of Each}:

60 da s

11. Hours In ReporL~g Period

12. Yumber Of Hot44s Reactor Has Critical

13. Reactor Reserve Shutdovn Ho--~

14. Hours Generator On-L'~e

15. Urdt Reserve Shutdown Ho-a

16. Gross Tl.camel Energy Gene.

t d (NISH) 17.

Gross

}earn""IEnergy Gere.

r (441'O'H)

IS. Yet Electri

}Ence y Generat d ( IViH)

19. Unit Servic" Factor

30. Unit Avai}abi!}y4 Factor 3". Urit Capacity Factor (Using DER Yet)

23. Unit Forced Outaoe Rate 3~. Shutdowns Scheduled Over 4'ex: 6 Months (Type. Date. cnd October 22, 1979 Refuelin

'Outa e

15 3ll 10,624.7 0

10,046.7 9 666 04 9,296 204

79. 6 7.6 72 '

71.3 14.5 "5. IfSh.: Do-'n At nd Of R"port Period, Estimated Date ci Startuo.

'5. Units In Test Status IPrior to Commercial Operation}:

Forec" st Ach1cved IYIT}AL CP.iTiCALITY IYITIALE.'CTRICITY CO.'VIE? CIA} OPERATIOY

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UNITSIIUTDO'lUNS AND POIUER REDUCTIONS

~5..

1979 DOCKET NO 50-31 6 UNI'rNAhfr 0 C. Cook-Unit 2 COhlPLETED Df B.A. Svens son

~S4 S-Dale ll ~

g t)

~ I/) g a

Liccoscc Event Rcport 4 C+

Q 0 Ii) Cr c )

o 4J Q

e) 2 ~

0(J Cause &. Cofic).t ivc Action II)

Pfcvcol Rccuffcocc 61 62 63 790908 790915 790929 0

8 S

26.9 0

N.A.

N.A.

N.A.

Zz Zzzzzz ZZ ZZZZZZ HH PUMPXX Reactor power reduced to 705 to per-form N. I.S. incore/excore cross cal-ibration.

Power returned to 100%

790909.

Unit removed from service due to low oil level alarms on reactor coolant pump motor bearing oil reservoirs.

Reactor power returned to lOOX 790916.

Reactor power reduced to 53K to re-move the east main feed pump from service due to high bearing vibration.

Reactor power returned to lOOX 791001.

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Forced S: Schcdiilcil (I)/77)

Rcasi)n:

A.EI)uipn)cnt Failure (Explaiii)

D-Maiiitcnance or Test C-Rcfuclh) g D-Regulatory Restriction E OpcfiilofTfahlhlg & Uccnsc I:xan)inatioll F.Adnlinistralivc G Opcralioilal Eiror (I'.xplaiii)

Il.other (Explaui)

Method:

I -Manual 2.Manual Scrain.

3.Aulonlat lc Scfiuu.

4-Other (Explain)

Exhibit G - Instructions for Preparatioii ol'Data Entry Shccls I'or Licensee Event R.p>>ft (LER) riic (NURi;G-OI6I)

'L'xliibilI - Sainc Source

UNITSHUTDOWNS AND POWER REDUt. IONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source of explan.

ation of signiticant dips in average power levels.

Each signi-ficant reduction in power level (greater than 20% reduction in average dally power level for the preceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even though the unit may not have been shut down completelyi.

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 exphin.

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 I'or both report periods to be sure Jl shutdowns or significant power reductions are reported.

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

DATE.

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

Report as year. month, and day.

August 14. 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 reductions are reported.

TYPE.

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

du!ed," 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.

DURAT101<I.

Self~xplanatory.

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

Report duration 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.

Catep>rice by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. supply briei'comments.

METHOD OF SHUTTlNG DOWN THE REACTOR OR REDUCING POWER.

Cate<torize by number designation INote that this differs irnm the Edison Electric Institute

{EEI) definitions of "Forced Partial Outage-and

-Sche-duled Partial Outage."

For these tern>>. 1:Fl uses a change oi'0 MW as the break p<>ini.

F<>r Iar<ger power reactors.30 MW is t<><> small a change to warrant cxpianati<>><.

in accordance with the table appearing on the report forin.

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 (NUREG416l).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.) If the 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).

SYSTEM CODE.

The system in which the outage or power reduction originated should be noted by the two digit cod>> of Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416l).

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.

CO<<IPONENT CODE.

Select the most appropriate component I'rom Exhibit I

~ Instructions 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 &:CORRECTIVE 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-

'te.

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 ihe critical path activity and a report of any single release of radioactivity or single radiation exposure specitically associ

~

ated with the outage which accounts for more than 10 percent oi the allowable annual values.

For long textual reports continue narrative on separate paper and re!'<'.ren<.e tiie shutdown or power reduction for this illffJ ilve.

(<)/77

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R.

S.

Lease (616) 465-5901 October 11, 1979 1 of2 MONTHLY OPERATING EXPERI',ENCES -- SEPTEMBER, 1979 Hi hli hts The Unit operated at 100K power the entire reporting period except as noted in the summary.

There was one outage during the reporting period.

This is also detailed in the summary.

Total electrical generation for the month was 723,270 Nwh.

Summar 09/08/79 -- Power was reduced to 70/ over a 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br />.

This was to perform an Incore/Excore Nuclear Instrumentation Cross Calibra-tion.

Power was returned to 100/ over a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ramp starting at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> 9/09/79.

09/15/79 -- The Unit and the Reactor were started down, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and removed from service at 0327 hours0.00378 days <br />0.0908 hours <br />5.406746e-4 weeks <br />1.244235e-4 months <br />.

This was a scheduled outage and the purpose was to refill three Reactor Coolant Pumps'ubricating Oil Reservoirs that had been operating on a low-level alarm."'he Reactorwas 'returned to criticality at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />.

09/16/79 -- The Reactor tripped due to low-low level of ¹3 Steam Generator at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />.

The Reactor was returned to criticality at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />.

The Turbine was rolled at 0438 hours0.00507 days <br />0.122 hours <br />7.242063e-4 weeks <br />1.66659e-4 months <br /> and paralleled to the system at 0622 hours0.0072 days <br />0.173 hours <br />0.00103 weeks <br />2.36671e-4 months <br />.,

The Unit was loaded to 100% power by 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

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Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit P2 R.

S.

Lease (616) 465-5901 October 11, 1979 2 of 2 09/26/79 -- Radiation Monitors R-l,l and R-12 were inoperable for a nine hour period due to pump failure.

09/29/79 -- Power was reduced to 53/. over an 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> ramp starting at.1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.

This was to remove the East Main Feed Pump from service due to excessive vibration at the Inboard Pump Bearing.

After the pump was removed from service Unit power was recovered to 58K.

After realigning the pump and lubricating the coupling, the East Feed Pump was returned to service at 0844 hours0.00977 days <br />0.234 hours <br />0.0014 weeks <br />3.21142e-4 months <br /> 10/01/79.

Starting at this time power was returned to 100/ over a

5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ramp.

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DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D.

C.

Cook - Unit No.

2 10-12-79 B. A. Svensson 6 6 465-5901 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1979 M-1 M-2 CSI-1 CRI-2 CSI-3 C&I-4 CSI'-5 No.

1 steam generator blowdown containment isolation valve, DCR-310 closed for no apparent reason.

A hole was discovered in the diaphragm of the valve operator.

Replaced the diaphragm and had valve retested.

No.

3 boric acid transfer pump suction valve, CS-414-3, was leaking.

Re-placed valve diaphragm.

Radiation monitor R-ll and R-12 sample pump failed.

Replaced pump with a spare and tested pump for proper operation.

Detector "F" on the flux mapping system would not operate in the in-sertion mode.

The time valve was not being printed on the axial power distribution system recorder.

Relay K82A was replaced to correct the operation problem on 'detector "F" transfer system.

The operation of the detector "F" transfer system was functionally tested.

The APDMS real time clock was replaced with a spare clock.

j During the testing of "C" main turbine stop valve, the control valve closed prior to the stop valve closure.

The stop valve's closed limit switch indicated a closed position while the valve was in the open position.

The closed signal resulted in the control valve responding prior to the closure of the stop valve.

The limit switch was manually operated until freedom of movement was verified.

A retest of the valve demonstrated the operability of the limit switch and circuits.

The solenoid for the main turbine stop valve "B" failed.

The coil of the acutation solenoid had failed.

A spare solenoid was installed.

The stop valve closed limit switch would not operate upon the closure of the valve.

The limit switch was manually cycled until freedom of movement was verified.

A functional test was performed and demonstrated normal valve and limit switch operation.

Pressurizer pressure high reactor trip bistable, indicated a set point drift problem existed.

A spare bistable was installed to replace 2PB-455A.

The calibration of the bistable to the correct set point was performed.

The nuclear instrumentation system power range channels N41, N42, N43 and N44 were calibrated based on the latest incore/excore calibration date of the Nuclear Section.

The aT-Tavg flux penalty modules were also cal-ibrated based on the axial offset values versus detector current data.

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DOCKET NO.

UNIT NAME

'ATE COMPLETED BY TELEPHONE PAGE "50 316 D.

C.

Cook - Unit No.

2 10-12-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1979 MFC-141, P4 Steam Generator steam flow was spiking high, thus giving a steam flow feed flow mismatch.

The steam flow square root extractor was found to be spiking on the output.

It was replaced with a new module and calibrated.

The timer on the "A" diesel fire pump battery charger wouldn't shut the charger off, causing the batteries to boil dry.

The transistors in the saturable reactor board were discovered to be blown.

The transistors were replaced and correct operation was verified.

R-ll and 12 pump failed and could not be restarted.

The pump was found locked up.

A new pump was installed and tested for proper operation.

MRY-232, test valve on k'3 Steam Generator stop valve would not test.

The coil for solenoid valve XSO-232 was found open.

The coil was replaced and proper operation of MRV-232 was verified.

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