ML17318A436

Monthly Operating Rept for Oct 1979

ML17318A436
Person / Time
Site:	Cook
Issue date:	11/01/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17318A435	List: ML17318A433 ML17318A436
References
NUDOCS 7911200400
Download: ML17318A436 (12)

Text

OPERATIC DATAREPORT DOCi'~T NO.

DATE COifPLETED BY TELEPHONE 624EHk901 OPERATING STATUS I. Unit Yame DOn ld

2. Repor.'In Period-OCtOber S. Licensed The....J Powe. (MNt):

4. nameplate Ratin~ (Gross M)Ve):

S. Desi~ Efecm~l Ra'.Ing (Yet (iIVY'e):

.6. ~fa".imum Dependable Capacity (Gross )IKe)t 7..'ifaxirnum Depend" bl Cap city (bet MNe):

1 7 3250 1089 1054 1

4 itous S. IfChanges Occ r in Capacity Rat'os (lt ms {umber S Throu~~. 7) Sine Last Repor.. Give Reasons:

9. Power Level To Vlhich Restricte", IfAny ( tet lfVie):

IO. R asons For Resa.'ctions, IfAny:

This Month Yr.-to-Date Cumt:lative

11. Hou:s!n Repo-..:~g Period IZ. Number Of Hours Reactor u."as C;tical IS. Re"c'.or Reserve Shutdown Hour

14. Hou;~ C nerator On-Line IS. Unt Reserve Si:utdown iio" ~

16. Gross Thermal Enemy Cene. t "(M')'/H)

17. Gros Eie"trice! ""aer"y Generated

(!~f1YH)

IS. Yet Ei 0:r'c"I Ene.~y Cenem: "(Vi'AH)

19. Unit Service F ctor ZO. Unit Availability Factor

21. Unit Capacity Factor (Usin"- l(tDCYet}

2". Urit Capacity Factor (Using D R Ye!)

'S. Unit Forced 0 "tape Rate "4. Shutdowns Sche'uled 0'er Next 6 Mon:hs 745 638.7 0

0 470.8 0

4,637.9 2 067 631 685,240 4 788 790 661,623 4,618 915 85.7 85.7 63.6 63.6

84. 3 60.0 9

14.3

{Type. Date. and Du:ation of Each):

463 31,051.2 321 26 95602 75.3

75. 3

61. 8 "S. liSh; Down At Fnd Oi Re:ort P.;iod. Estimate

-0 t of Startuo:

5, Units I:1 Test Status f Po 0

\\0 Com~r~Ie,cial Op tao> )t Foea~~st

$ c4 iWg JhA fTIAL CR; TiC, I.lTY

~

+ IMtf'V CO: )i>ERC)AL OPERATiO,"

• -ZO to correct er) or on March Report Dated 4-4-79

{(l/() )

rg9yg000 PCRP-

AlcRACc DAlLYLAITPO4cR

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DOC~i ~O L

hali DAL=

616-'4.65-5901 October 1979 DAY Ay~AC:- DAlLYPONFR LiyEL (M'h~get)

I 1039 1041 DAY AyiRACr.DAlLYPONiR L y:"'MNe,'ie!

)

1039 1039 1039 1038 1038 l9

')0 1032 1020 1038 1040 1037 l0 1039 1038 1037 1041 1038 o5 o9 30 31 104 0

0 0.

l4STRUCi )ONS 0".!.".:5 Qc..El.::v

."ae ave."v

="I!a'".!E -i:<<'e: le"-!:

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-: "-: led e."a -<y i,"..:,e: :.~-,-,),g.C,>(gg; a,'le fless si v'ilcl>>..)esxN'

UNITSIIUTD01VNS AND P01VER REDUCTIONS REPoRThloNTII October, 1979 DOCKET NO.

. A.

,. TEI EPIIONE 616 465-5901 I

~

~

No.

Dale

~III CSL ri IArjJ II ~

~ VI Liccnscc Event Rcport 4 C<

4J El

'O rri G

~I/lQO Eu O

Cause &Corrective Action lo Prevciil Rccurrcncc 152 791027 F

105.3 1/3 N.A.

ZZ ZZZZZZ Unit removed from service to repair No.

4 Inverter and add oil to No.

4 Reactor Coolant Pump Motor Upper Oil Reservoir.

Unit brought to cold shutdown condition to permit inves-tigation/repair of cause for high vibration on R.C.

Pump No. 12.

Unit remained out of service at the end of the month.

I': Forced S: Scbcdulcd Reason:

A-EIIuipnicnt Failure (I'.xplain)

II-hlaiiilcnance or Test C-Refueling D.l<<t,ulatory Restriction E.OI)cfillofTraining & Uccnsc I:xai))ination F-Adniinislialivc G-Operational Error (I'.xplain)

~ I I Oilier (Explain) h(cthod:

I-Manual 2.hlaiiual Scrani.

3 Aiifolliattc Scfani.

4-Otltcr (Explain)

Exhibit G - Instructions fiirPrcparatiiiii iil Data Entry Sliccts for Lieciiscc Event Reprirt (I.LR) File (NURI:G-016I )

Lxhibit I - Saiite Source

UNITSHUTDOWNS AND POWER REDU

~ iONS 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 thah

>Otic reduction in average 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 />) 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 all shutdowns or signitioant 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 significant power reduction.

Report as year. month. and day.

August i4. 1977 would be reported as 770814.

When a shutdov n or significmt power reduction begins in one report period and ends in ~mother, an entry should be made for both report periods to be sure all shutdowns or significant power reductions 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 oif.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.

Seif<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 th>> 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 t'orm. Ifcategory H must he used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Caiegorize by number designation INioie that this dift'ers irom the Edison Electric Institute (EEI) deimitions ot'Forced Partial Outage-and

-Sche-duled Partial Outage."

Fi>r'these iern>>."FEI uses a change ot'0 MW as the break point.

F>>r larger power reactors. 30 MW is ii><> small a change ti> warrant cxpianaiii>n.

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 (NUREG4161).

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 hot applicable (N/A).

SYSTEM CODE.

The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

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 - Instructio'ns for Preparation of Data Entry Sheets for Licensee Event Report (LER) File {NUREG416l).

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 rnai-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 ampiify or explain the circumstances of the shutdown or power re'duction.

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 radioaI:tivity i>r single radiation exposure specitically associ

~

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

For long textual reports'continue nairative on separate paver and reference tiie shutdown or power reduction for this liafratlve.

UNITSHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe Jl plant shutdowns during the report period.

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

Each signi.

ficant reduction in power 1 vel (gr ater than 20zc reduction in average daily power levc! for the prec ding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even thouah the unit may not have been shut down completeiyl.

For such reductions in power level, the duration should be Usted 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 Correc:ive 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 signiiicant 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 all shutdowns or si>mif>cant 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 i '. 1977 would be reported as 770814.

When a shutdown or signif>cmt power reduction begins in one report period and ends in nother, an entry should be made for both report periods to be sure all shutdowns or signif>cant power reducuons arc 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 tha! some judg-ment is required in categorizing shutdowns in this way.

In general.

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

DURATION.

Seifwxplanatory.

When a shutdown extends beyond the end ot a report period, count only the time to the cnd oi the report period and pic'p the ensuing down time in the following report periods.

Report duration of outages rounded to the nearest tenth vfan hour to facilitate summation.

The sum ot the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.

REASON.

Categt>rizc by letter designation in accordance with the table appe ring>>n the report torm. Ifcategory H must be used. suppiy brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that this ditYers

>rom the Edison Electric Institute (EEI) deiinitions oi -Forced Partial Outage" and

-Sche.

duled Partial Outage.-

F>>r these

>enn~. FEl uses a

~i>ange->>t'0 MW as the break point.

F>>r larger power reactors. 30 MW is >ii'> small a hange u> warrant explanaiio>>.

h> accordanc with the table appearing on the report form.

Ifcategory 4 must be used. supply brief comments.

LICENSEE EVENT REPORT

=.

Reference the applicable reportable occurrence penaining 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) Fiie (NUREG4161).

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 code of Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (>>1UREG4161).

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

COMPONE>NT CODE. Seiect the most appropriate coinponent I'rom Exhibit I - Instrucuons for Preparauon of Data Entq Sheets for Licensee Event Report (LER) File (NUREG4161).

using the followingcritieria:

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

B.

If not a component faiiure. 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 mai.

. function should be listed. The sequence of events. includ-ing the other components which fail, should be described under the Cause and Corrccuve Action to Prevent Recur.

rene 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 h> a narrative fashion to ampiify or explain the circumstances oi the shutdown or power reduction.

The column should include the specific cause f'r each shut-down or signif>cant 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.rc!ated corrective maintenance performed during the outaae or power reduction including an identification of the critical path activity and a report of any single release ot radioac:ivity vr 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 reference the shutdown or power reduct>on for this ilafrativc.

I~)!77

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 81 R. S.

Lease (616) 465-5901 November 14, 1979 1 of3 MONTHLY OPERATING EXPERIENCES -- OCTOBER, 1979 Hi hli hts The Unit entered the reporting period operating at lQOX power and continued to do so except as noted in the summary.

The Unit was removed from service for a scheduled outage 10/27/79 and remained out of service the remainder of the reporting period.

Total electrical generation for,the month was 685,240 Nwh.

Summar 10/02/79 -- The Diesel Driven Fire Pump was returned to ser-vice at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />.

This pump had been removed from service at 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br /> 9/19/79 for overhaul.

10/08/79 -- Containment Recirculation Sump started showing an accumulation of water.

Pump-out and analysis of this water indicated it to be secondary side leakage rather than primary.

Reactor coolant leakage remained the same at 0.4 gpm.

Leakage into the sump was calculated to be 0.4 gpm.

10/ll/79 -- The Spent Fuel Pit Ventilation Exhaust System was made inoperable at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> for replacement of the charcoal filter material.

This system was returned to operable at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> 10/17/79.

10/12/79 -- The normal reserve power source to Auxiliary Transformer 101AB was out of service for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period,to make repairs to an underground cable.

This cable had been dug into while making an.excavation in the plant yard.

'The actual cable damage was minor but did require repairs.

This source also supplies the 201AB Transformer on Unit 2 so it was also inoperable the same length of time.

10/13/79 The 5'4 Reactor Coolant Pump low level oil alarm started annunciating.

This was identified to be the upper reservoir of the motor.

The oil level was monitored by installed television and was still adequate.

I i1

~ ~

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 81 R.

S.

Lease (616) 465-5901 November 14, 1979 20f 3 10/16/79 The k2 Steam Generator Stop Valve Dump Valve HRV-221 was inoperable for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period to repair a steam leak.

10/18/79 10/19/79 10/21/79 The Motor Driven Auxiliary Feed Pump was inoperable for a 2.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period for lubrication.

The 150 Foot Wind Direction Recorder was out of service for a 0.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period for" repairs.

This outage was common to both units.

The 150 Foot Wind Direction Recorder was out of service for a 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> period for repairs.

This outage was common to both units.

Power was reduced to 85/ for testing of Hain Turbine Control Valves.

Total time below 100Ã level was 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

10/22/79 10/27/79 The 150 Foot

- Wind Direction Recorder was out of service for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for repairs.

This outage was common to both units.

The Unit was released for a scheduled outage at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />.

Intentions were for a normal load reduction outage, however, the Unit tripped from 50/ power at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> due to a high level in the right Moisture Separator.

Reason for the outaqe was to add oil to the upper reservoir. of thek4 Reactor Coolant Pump, locate and repair the source of secondary leakage reported 10/08/79 and to investigate excessive vibration in the 82 Reactor Coolant Pump.

Also intended during the outage was to replace the oscillator card in the b'4 instrument bus inverter-and to repair a

leak in the stator cooling water system of the Main Generator.

Condenser Air Ejector Radiation Monitor R-15 was inoperable for a 5.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period.

'l f0:<".)L.D." ~

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit Pl R. S.

Lease (616) 465-5901 November 14, 1979 3of3 10/28/79 It was decided it was necessary to cool down and drain down the Reactor Coolant System to make repairs to the k'2 Reactor Coolant Pump.

Degassing of the system was initiated at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> and cool down at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br />.

10/29/79 -- The Reactor Plant entered Mode 5 at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />.

10/30/79 -- The Reactor Coolant System was drained to 1/2 loop.

The 34.5 KV power source to Transformers.101AB and-101CD was de-energized at 0831 hours0.00962 days <br />0.231 hours <br />0.00137 weeks <br />3.161955e-4 months <br />.

This also removed the power from Unit 2 Transformers 201AB and 201CD.

Both units at this time were receiving 4KV auxiliary power from their normal power source.

This was accomplished by removing links between the Main Generator and the Main Transformer.

The reason for this outage was to make modifications to the 34.5 KV switchyard that supplies this normal reserve power.

Modifications were completed and the reserve power source of both units was returned to operable at 1718 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.53699e-4 months <br /> 11/01/79.

The source of secondary leakage was identified to be on a 3/4" level tap of b'1 Steam Generator.

Welding repairs were made.

r p1

~

.(o fgll f

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 315 D.

C.

Cook - Unit No.

1 11-13-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE

OCTOBER, 1979 M-1 No.

2 steam generator stop valve dump valve, MRV-221 was leaking.

Re-placed valve seat, machined plug and reassembled with new gaskets.

Had valve tested.

M-3 C&I-1 C&I-2 C&I-3 Oil was found in the AB diesel generator "AB2" starting air receiver.

Investigation determined oil to be coming from the air compressor.

Replaced the "lAB2" air compressor.

The root valve for Pl steam generator level instrument, BLI-110Vl was leaking at a socket weld.

Repaired by welding and had required NDE performed.

MRV-233, No.

3 steam generator power-operated relief valve was leaking when in auto.

The valve could be closed manually.

The valve's stroke was tested and indicated a problem with the pneumatic relays.

The pneumatic relays required disassembly and cleaning.

Following re-assembly and installation of the relays, calibration was performed, and correct valve operation was achieved.

BLP-130, No.

3 steam generator pressure channel failed low.

Problem was traced to the penetration feed-throughs.

The penetration feed-throughs were changed, and proper operation verified.

hT/Tavg, Loop 2 was found to be out of spec.

when performing surveil-lance test.

TY-421A, bistable was found to be out of spec.; it was replaced and calibrated.

Proper operation was verified, and the loop was returned to service.

C&I-4 C&I-5 A non-urgent failure alarm on the rod control system was received in the control room.

A power supply fuse in the logic cabinet had opened.

The blown fuse indicator on the opened fuse failed to indicate the condition.

A spare fuse was installed.

Loose contacts on the alarm circuit board in the power cabinet also produced the non-urgent failure alarm.

The contacts were cleaned and tightened.

Steam Generator No.

4 level protection channel III indicated 6X greater than the adjacent channels.

BLP-142, Barton reverse-acting requalified transmitter was replaced with a spare transmitter.