ML17317B337

Monthly Operating Rept for June 1979

ML17317B337
Person / Time
Site:	Cook
Issue date:	07/05/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B336	List: ML17317B335 ML17317B337
References
MOR-790630-1, NUDOCS 7907200333
Download: ML17317B337 (12)

Text

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0-AVERAGE DAILYUNITPOWER L VEL DPCyrT qP 50-3't 6 UNIT

~7 COMPLETED IIY W.T. Gillett T=L~oHOr'E 616-465-5901 June 1979 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net I I

0 0

DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) 0 0

10 13 I6 0

0 0

0 0

0 0

0 0

0 0

0 0

0 19 10

'79 30 31 0

0 0

0 0

0 0

0 0

0 0

0 INSTRUCTIONS pn this format. list th av raze cail( un!t power lei'e! tn II~Ve.Net for each nay in the rePort:nz month. Compute to'he nearest whole m aawatt.

(c)IT /)

OPERATE G DATAREPORT T rrrO 50 316 DATE COMPLETED BY ett TELEPHONE

" 901 OPERATING'STATUS Donald C.

Cook 2

3. Licensed Thermal Power PDVt):

4. Nameplate Racing (Gross llDVe):

S. Design Eiectricai~g (Nec irlÃe):

6. Klaximum Dependable Capacity (Gross hinge) c

7. Maximum Dependable Capacity (Net MWe):

33 1

1133 1100 18 1082 Notes

8. IfChanges Occur in Capacity Ratings (Items Number 8 Through 7} Since Lasc Reporc. Give Reasons:

9. Power Level To which Restricted, IfAny (Net ilDVe}:

10. Reasons For Restrictions, IfAny:

11. Hours ln Reporting Period IZ. Number Of Hours Reactor Vhs C.":tical

13. Re ctor Reserve Shutdown Houa

14. Hours Generator On-Line IS. Unit Reserve Shutdown Houts

17. Gross Electrical Energy Geaemted (ilIWH)

18. Net Electrical Ene~ Generated (MNH)

19. Unit Servic Factor

20. Urit Aiadability Factor

21. Unit C"pacicy Factor (Using MDC Net)

22. Uait Capacity Factor (Using DER Net)

'H.

Unit Forced Outage Rate

24. Shutdowas Scheduled Over Next 6 i~lonths (Type.

This Month 720 0

0 0

Yr..to-Date 4;343 3,260.

0 3 203.7 0

10,558,347 0

0 0

0 100 Date. and Dumtion of Each):

73. 8

70. 6

69. 5 26.2 0

3 318 379 Cumulative 13,103 8 491.1 0

7,93.3 23 663 454 7 422 460 7,132,378 75.5

68. 0

66. 8 17.4 S. IfShut Down Ac End Of Report Period. Estimated Date of Startup:

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25. Units ln Test Status {Pnor to Commercial Operationn Force"st Achieved INITIAL CRITICALITY INITIALELECTRICITY COMMERCIALOPER ATIOr'4 Iolr r)

UNITSIIUTDO'IVNSAND PO)VER REDUCTIONS REPORT hIONTII JUNE, 1979 DOCKET NO.

DATE 7-11-79 COhIPLETED I)y B.A. Svensson TEI.FPIIONF 616 465-5901

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gp~ CR I Iccnscc Event Rcport e Cause & Correct ivc Action to Prevent Rccurrcni:c 59 790519 720 1

79-01 9/0]T-0 FH PIPE XX The Unit was removed from service on Hay 19, 1979 to repair cracks in the 16 in. feedwater elbows adjacent to the feedwater elbow'/steam generator nozzle weld on the four steam genera-tors.

The Unit remained out of ser-vice at the end of the month.

F: lorced S: Schedulcil

{')/77) l{casi)ll:

A.Eilllli)nlcnlFalhlrc (Explain)

Il.hlai>>tcnance oi Test C-Refueling I)-I{cgulatoiy Rcslrietion

':-Operator Training & License I:xarnioation F-Adlninistlative-G.OI)cratlonal Lrri)r{Explahl)

II.Other (Explahi)

Method:

I.Manual 2 hlai)ual Seraln.

3-Autoinatic Serai>>.

4-Other (Explain)

Exhibit G - instructions fi)r Prcpar Jtlinl of l)ata Lntry Shccts for Lice>>sec rvcnt Report {I.l!R)File INURI.:G-OI6I )

'Exhibit I - Salne Source

UNITSHUTDOWNS AND POWER RE TIONS 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 2&o 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 completely i. 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 Correcuve 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 ail shutdowns or signiiicant power reductions are reported.

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

DATE.'his column should indicate the date of the start of each shutdown or significant power reduction.

Report as year. month. and day.. Auzust 14. 1977 would be reported as 770814.

When a shutdown n 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-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.

Selfwxpianatoty.

When a shutdown extends beyond the end of a report period, count only thc 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 oi 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 tabie appearing un the report t'orm. Ifcategory H must he used. supply briei'omments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that this ditt'ers trom the Edison Electric Institute (EEI) detinitions of -Forced Partial Outage" and

-Sche-duled Partial*Outag<<."

For tlies<< t<<rtn~. FF I uses

~ <<hange ot'0 MW as the break point.

For larger power reactors. 30 MW is n>>i small a change to warrant <<xplanatii>>i.

'n 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.) Ifthe outage or

- power'reduction wiU 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 ot Exhibit G - Instructions for Preparation of Datz 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 bc used for those events where a system is not applicable.

COMPONENT CODE.

Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

using the following critieria:

A. 'fa 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 comoonent.

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 thc 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

corpponent designation is not applicable.

CAUSE Ec CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative fashion to ampiify 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 of radioactivit) or single radiation exposure specitically associ

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

I,c For long textual reports'continue narrative'on separate paoer znd ref<<ren<<e tlie shutdown iver power reduction ior this IlarfJtivc.

SHUTDOWNS AND POWER REDUCTIO.

INSTRUCTIONS f port should describe Jl plant shutdown ns curing the fepori period.

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

Fach signi-ficant reduction m power level (greater than 2Pic 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 thouph the unit may not have been shut down completely1.

For such reductions in power level, the duration should be listed as zero. the method of reduction should be listed as 4 (0'her), and the Cause and Corrective Action to Prevent Recurrence column should exphin.

The Cause and Corrective Action to Prevem Recurrence column should be used to provide any needed expianation to fully des"ribe the circumstances of the outage or power reduction.

NUI>IBER.

This column should indicate the sequential num-ber assigned to eacn shutdown or sLaniftcant 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 a0 shutdowns or signiiicant po~er 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.. Auaust i4. 1977 would oe 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 a0 shutdowns or significant power reductions are reported.

TYPE.

Use "F" or -S" to indicate either <<Forced'-'or "Sche-duled." respectivelv, for each shutdown or sipnlf>cant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend fo0owinp 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 compieied in the absence of the condition for which corrective action was taken.

DURATION.

Selfcxplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end oi the report period and pick up the ensuing down time in the fo0owing report periods.

Report auration of outapes rounded to the nearest ienth ofan hour to faciTitate summation.

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

REASON.

Categorize by letter designation in accordance with the tabie appearinp on the rept>rt torm. If category H must be used. supply brie>

omments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCII>>>G POWER.

Cateponze by number designation Note that this diiTers irom the Edison Electric Institute tEEI) deimitions of -Forced Partial Outage" and

-Sche.

duled Partial Outa>t>>."

F>>r ihes>> ter>its. I:El uses a

ciianpe>>t'0 MW as the break p>>>nt.

F>>r larger pose> reactors.SOMW is i

>.> ~n>ail a hanpe t>> v ar>ant expianati>u>.

in accordance with the table appearing on the report form.

Ifcategorv 'ust oe used. supply brie.'comments.

LICENSEE EVENT REPORT =.

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

Enter the frst four parts (event year. sequential report number. occurrence code and report type) of the five part designation as described in item 17 of Instruciions for Preparation of Data Entry She ts.for License Event Report..

(LER) File (NUREG4161).

This information may not be immediately evident for a0 such shutdowns, of course, since further invesugation may be reouired to asc rtain whether or not a reportable occurrence was involved.) If the outage or power reduction wi0 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 oriainated should be noted by the two digit code of Exhibit C - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (N>>UREC416I).

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 - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File {NUREC4161).

using the fo0owing critieria:

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

B. If not a component faiiure. use the related component:

e.g..

wrong valve operated tnrough error: list valve as comt>onent.

C.

If a chain of failures occurs. the first component to mai ~

function should be listed. The seauence oi"events. includ-ing the other components which fail. should be descrioed under the Cause and Corrective Action to Prevent Recur-rence coiumn.

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

sipnated XXXXXX. The code ZZZZZZ should be used for events wnere a

component designation, is not applicable.

CAUSE Ec CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Us: the column in a narrative fashion to ampiiiy or explain the circumstances oi the shutdown or power rediuction.

The column should include the specific cause for each shut ~

down o. significant power reduction and the immediate and contemplated lone tertn corrective action taken. if appropri-ate.

This column should also be used for a description of the major safety-related corrective maintenance performed during the outage or power reduciion includinp an id ntification ot the critical path a>>tivity and a report of any single release of radioac:ivity ur sing/e radiation exposure sp

'it>."ally assoc>

~

ated with the outage which accounts for more than 10 percent of the a0owabie annual values.

For long textual reports continue nar.ative on separate naoer m~u rei'erence the shutdown or power reduct>on ti>> tnl>

nar. Jtive.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R.

S.

Lease (616) 465-5901 July 13, 1979 1 ofT, MONTHLY OPERATING EXPERIENCES -- JUNE, 1979 Hi hli hts This Unit has been in Mode' operation the entire reporting period except as noted in the summary.

Repairs and modifications of feed-water piping have been taking place:.

This problem was identified in the May report.

Summar 06/19/79 06/20/79 06/21/79 06/25/79 06/29/79 06/30/79

¹3 Steam Generator was successfully hydrostatically tested after repair of its feedwater piping.

¹1 Steam Generator was.successfully hydrostatically tested after repair of its feedwater piping.

¹2 Steam Generator was successfully hydrostatically tested after repair of its feedwater piping.

¹4 Steam Generator was successfully hydrostatically tested after repair of its feedwater piping.

Heatup of the Unit commenced with entry into Mode 4 at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />.

The Reactor Plant entered Mode 3 at 0947 hours0.011 days <br />0.263 hours <br />0.00157 weeks <br />3.603335e-4 months <br />.

At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> excessive lake water in/leakage was detected in the Condensate System.

The trouble was traced to several massive tube failures in the Main Condensers.

Contamination was so great that it requires draining all the Condensate System and its storage tank.

The Reactor Plant was held in Mode 3 with Auxiliary Feedwater source from Unit l.

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DOCKET NO.

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

C.

Cook - Unit No.

2 7-11-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE

JUNE, 1979 M-2 Non-essential service water to containment ventilation containment isolation check valve, NSW-417-4 failed to pass the leak rate test.

Cleaned valve internals and had valve retested.

1 Containment isolation valves for radiogas detector, ECR-31 and 32 failed to pass the leak rate test.

Lapped valve seats, cleaned inter-nals and had valves retested.

M-3 Containment isolation air sample check valve failed to pass the leak rate test.

Cleaned dirt from valve internals and reassembled.

M-4 Containment ventilation isolation valve, VCR-201 f'ailed to pass leak rate test.

Valve internals were cleaned and valve was reassembled.

Safety injection containment isolation valves, ICM-250 and 251 failed to pass leak rate tests.

Lapped the discs and seats, cleaned inter-nals and had valves retested.

Ventilation system containment isolation valve, VCR-105 and 205 failed to pass leak rate tests.

Cleaned and adjusted both valves and had them retested.

M-7 Ice condenser refrigeration containment isolation check valves, R-156 and R-157 failed to pass leak rate tests.

Cleaned valve internals and had them r etested.

Ventilation system containment isolation valves, VCR-104 and 204 failed to pass leak rate test.

Adjusted both valves to obtain tighter seal when closed and had them retested.

M-9 Safety feature safety valves discharge line containment isolation check valve, SI-189 failed to pass leak rate test.

Cleaned valve internals and had valve retested.

M-10 Service water containment isolation valves, WCR-962 and 967 failed to pass leak rate tests.

Cleaned both valves internally and had them retested.

Ventilation system containment isolation valves, VCR-103 and 203 failed to pass leak rate tests.

Cleaned valve seats and adjusted for tighter seals when closed.

Had valves retested.

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DOCKET NO.

4 50 316 UNIT NAME,-'.

C.

Cook Unit No.

2

DATE, 7-11-79 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 PAGE MAJOR SAFETY-RELATED MAINTENANCE

JUNE, 1979 Non-essential service water containment isolation valve, WCR-930 failed to 'pass leak rate test.

Replaced the valve seat and gaskets.

Had valve retested.

Containment ventilation drains. containment isolation valves, DCR-620 and 621 failed to pass leak rate tests.

Cleaned valve internals and replaced gaskets.

The valves tested satisfactorily.