ML17317B269

Monthly Operating Rept for May 1979

ML17317B269
Person / Time
Site:	Cook
Issue date:	06/04/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B268	List: ML17317B266 ML17317B269
References
NUDOCS 7906190243
Download: ML17317B269 (13)

Text

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AVERAGE DAILYUNI7 PO4 r.R L:-VEL DOCK=T VO. '0-316 2

DAT-.

6-4-79

~~~HONE 616 465 5901 p~

Ma 1979 I

DAY AVERACE DAILYPOKER LEVEL (M4'e.Net)

I 1048 1069 DAY AVERACE DAILYPO4'ER LEVEL (MWe.. iet) 786 1056 IZ I

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15 16 1071 10 1070 1066 1067 1063 10 1070 10 2

1069 1067 478 19

'WO ZI 24 55 15 ZS

'i9 697

~ 0 0

0 0

0 0

0 0

0 0

0 0

NSTRU~iONS Qq t!;it f0t...mt.'.It;;~i eiv t<<z

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OPERATIiiG STATUS OPERATL fG DATAREPORT DOCKET NO.

50-316 DATE ~Z9 COMPLETED BY ~~tt TEI.EPHONE

~61 -~901

l. UmtName Donald C. Cook 2

Reporting Period:

3. Licensed Thermal Power (MWt):

4. Namephte Rating (Gross MWe):

S. Design Electrical R"ting (Net MWe):

6. Xfaxfmum Dependable Capacity (Gross MWe)t

7. Maximum Dependable Capacity (Net MWe):

3391 1133 1100 1118 1082 Notes S. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricts, IfAny (Net ibfWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to-Date 744 3,623 3 260.4 0

0 434.1 3 203.7 0

0 10,558,347 1 449 347 471 680 3 436 930 456,078 3,318,379 58.3

88. 4

58. 3 ~

88. 4 84.7 56.7 83.3 55.7 41.7 13.1 IType. Date. and Dumtion of Each):

11. Hours ln Reporting period

12. Number Of Hours Reactor Was Cnticaf

13. Re ctor Reserve Shutdown Hours

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

16. Gross Thermal Energy Genemted (MWH)

17. Gross Ele~c 3 Energy Generated (MWH) 18.

Ne'er Electrical Energy Generated (.'rffVH)

19. Unit Service Factor

30. Unit AvaihbilityFactor "I. Unit Capably Factor (Using iifDCNet) 3". Unit Capacity Factor (Using DER Net)

~~. Unit Forced Outage Rate

34. Shutdowns Scheduled Over Next 6 Months Cumuhtive 12 383 8,491.1 0

7,931.3 0

23 663 454 7,422,460 75132,378 82.3

82. 3 7

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72.8 9.2

5. IfShut Down At End Of Report Pe:Iod. Estimated Date of Startup:

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'5. Units In Test Status IPrio to Commercial Operation):

Force" st Achieved INITIAL CRITICALITY INITIALELECTRICITY CO.'DIE? CIAL OPERATION

UNITSIIUTDOWNS AND POPOVER REDUCTIONS DOCKET NO.

50-316 A.

~6 No.

Ihtc

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~ V)

Liceiiscc I'Clit Rcport rr c

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Q D Ev O

Caiisc &, Corrective Aetio)1 lo Prcvcnt Rccorrciice 58 59 15.4 790519 F

294.5 790516 F

A H.A.

ZZ 79-019/01T-0 FH ZZZZZZ PIPE XX Reactor/Turbine trip due to steam flow/feedwater flow mismatch coinci-dent with low steam generator water level while performing surveillance test on Steam Generator No. 4.

The trip was caused by a momentary spike in the feedwater flow signal while the steam generator low level bi-stable was placed in the trip po-sition.

Reactor power returned to 1005 790517.

Unit removed from service to repair cracks in the 16 in. feedwater elbows adjacent to the feedwater elbow/steam generator nozzle welds on all four steam generators.

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

I': Foiced S: Schediilcil f))177)

Reasi)ll:

A-fiiuipmcnt Failure (Explain)

II hlaiiilcnancc oi Test C-Rc fi)cling

.D-I<eg))latoty Restriction E-Operator Training & Licciisc l)xatnii)ation I -Administ i at ive C.Opcralto))al Liror(I)xplain)

I I.Otlier (Explain) hlctliod:

I -Maiiiial

') hfanual Scrain.

3 At)till)IJ(fcScf llll.

4.Other (Explalll)

Exliibit G - Instructions for Prep:lr Jill)ll))fData I:ntry Sliccts fi)r Licciisec Event Rep<>rt (LLR) File (NUREC-Ol 6 I )

'l)xhibit I - Sanie Source

UNITSHUTDOWNS AND PO'IVER RE IONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.

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

Each signi-ficart reduction in power level (greater than 2Pio reauction 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 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 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 treduction.

NUMBER.

This column should indicate the sequential num-ber assigned to each shutdown or sienificant reduction in power for that calendar year.

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

an entry should be made for both report periods to be. sure all 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.

Aueust 14. 1977 would be reported as 770814, When a shutdov: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 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 off-normal condition.

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

In genera!.

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<xpianatory.

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 followine report periods.

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

The sum of the total outage hours plus the hours the genera-tor was on line snould 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 he used. supply brie)'omments.

METHOD OF SH UTTING DOWN THE REACTOR OR REDUCING POWER.

Caieg<<rize" by number designation IN<<ie that this dit'ters i'rom the Edison Electric Institute

{EEI) deimitions of -Forced Partial Outaee" and

-Sche.

duied Partidl Outage."

Fi>r ihese turin~. FEI uses u change oi'0 MW as the break point.

F~>r larger pi>v er reactors. 30 MW is n>>> small a chance ti> warrant explanaiii>>>.

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 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 (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.

COMPONENT CODE.

Select the most appropriate component from Exhibit I

~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

using the followingcritieria:

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 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 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 reduction.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated lone 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 outaee or power reduction including an identification of the. critical path activity and a report of any sinele release of radioactivity or sineie radiation exposure'specit>cally associ

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ated with the outaee which accounts ior more than 10 percent oi the allowable annual values.

J For lone textual reports iontinue narrative on separate

paoer, and reference tlie shutd<<ivn or power reductii>n for this llaffalive.

IL)/77

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit P2 R.

S.

Lease (616) 465-5901 June ll, 1979 1 of 2 MONTHLY OPERATING EXPERIENCES -- MAY, 1979 Hi hli hts This Unit entered the reporting period operating at 99% power.

The 821 Circulating Water Pump was out.of service due to bearing fail-ure.

With this pump out of service, the allowed hT across the Condensers was marginal.

Total electrical generation for the month was 471,680 Mwh.

,Summar 05/04/79 -- Power was reduced to 98% for a short period to test Turbine valves.

It was again returned to 99% power.

05/ll/79 -- 821 Circulating Water Pump was returned to service at 1628 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.19454e-4 months <br /> and Unit power increased to 100%.

05/12/79 -- Unit power was reduced to 99% for testing of Turbine valves.

Total time below 100% power was 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

05/16/79 The Unit and Reactor tripped at 100% power at 1147 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.364335e-4 months <br />.

Cause of the trip was low steam Generator level with steam flow/feed flow mismatch of k'4 Steam Generator.

The level was not actually low in the Steam Generator.

Surveillance testing was being per-formed that required tripping of the low level bi-stable.

While this trip was in the feedwater flow signal was spiked to cause the Unit trip.

The Reactor was returned to cri.ticality at 2247 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.549835e-4 months <br />.

. The Turbine was rolled, however, the Unit and Reactor tripped at 2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br /> while preparations were being made to parallel the..Generator with the system.

Caus'e of this trip was the Generator field breaker failed to close and the control switch was returned to normal.

05/17/79 The Reactor was returned to criticality at 0118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> and the Generator paralleled with the system at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />.

The Unit was loaded to 100% power by 1320 the same day.

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Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R. S.

Lease (616) 465-5901 June ll, 1979 2of2 05/19/79 -- Turbine valves were successfully tested at 1001 power.

The Unit was>'emoved

-from service with tripping of the Turbine at 1728 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.57504e-4 months <br /> and tripping of the Reactor at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />.

Leakage inside of Containment had started indicating 5/17/79.

Early analysis indicated the leakage to be service water.

By the time the decision was made to take the Unit out of service, the analysis of the water being pumped from the Contain-ment sump had turned to indicate Condensate.

Internal inspection found feedwater leaks on the feed-water lines close to Steam Generators 1

and 4.

Cool-down of the Reactor Coolant System was initiated at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> with entry into Mode 4 at 0113 hours0.00131 days <br />0.0314 hours <br />1.868386e-4 weeks <br />4.29965e-5 months <br /> 5/20/79, and into Mode 5 at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br /> the same day.

The cracks in the feedwater lines were adjacent to the weld that attaches the piping to the Steam Generator nozzles.

1lhile the cracks on Steam Generators 1

and 4

were totally through the piping, radiographs indicated there were also cracks in the. same general area on Steam Generators 2 and 3 but they had not propagated clear through the wall.

The elbows 'that connect the feedwater piping to the steam generator are being replaced on all 4 Steam Generators.

The new elbows are being modified to have a heavier wall thickness where the cracks had developed.

The Unit remains out,of service for these feedwater.

modifications.

T

DOCKET NO.

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

C.

Cook - Unit No.

2 6-13-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1979 M-1 M-2 M-3 M-5 M-6 CSI-1 C&I-2 No.

3 boric acid transfer pump had excessive seal leakage.

The mechanical seal was replaced.

Retest following repairs was satis-factory.

No; 3 steam generator main steam pressure instrument root valve, MPP-231-Vl was leaking.

Repacked valve and replaced the body-to-bonnet gasket.

No.

4 S/G 'main steam pressure test point root valve MPX-240-Vl was.

leaking.

Replaced valve bonnet.

No.

2 S/G main steam pressure instrument root valve MPI-221-Vl was leaking.

Repacked valve, replaced one packing gland bolt and re-placed body-to;bonnet gasket.

Loop 4 letdown regulating valves, gRV-ill and 112 had packing leaks.

Repacked both valves.

No.

2 steam generator pressure instrument root valve, MPP-212-Vl had a packing leak which resulted in a steam cut in the valve.

Replaced the valve stem, disc and gasket.

Air particle radiogas detector discharge line containment isolation

valve, ECR-33, failed to pass leak rate test.

Valve was cleaned and new gaskets were installed.

Valve tested satisfactorily.

Service water containment isolation valves, WCR-921 and WCR-934 failed to pass leak rate test.

Cleaned valve internals, lapped the seats and installed new gaskets.

Valves were tested satisfactorily.

Radiation Monitoring System Channel R-25, air pump failed.

The low flow and high flow relays which interlock the pump were relocated to reduce the vibrations imposed on the relays.

Correct operation of the R-25 Channel was verified and returned to normal operation.

The CCRP inverters output frequency varied from 60.1 to 61.0 Hertz.

As the inverters cabinet door was opene'd, the inverter returned to synchronous operation at 60.0 Hertz.

The ambient air temperature of the room was measured at 98oF while the air temperature within the cabinet measured 103 F.

A blower was placed in the room to reduce 0,

the air temperatures.

The CCRP inverters synchronization adjustment will be performed during the next outage.

DOCKET NO.

UNIT,NAME DATE

'OMPLETED BY TELEPHONE PAGE MAJOR SAFETY-RELATED MAINTENANCE MAY, 1979 50 316 D.

C.

Cook - Unit No.

2 6-13-79 B. A. Svensson 616 465-5901 The rod position indication system for rods P-8, F-10, K-10, K-6 indicated full scale.

The signal conditioning modules for each channel were calibrated and returned to service.

Main turbine stop valve B indicated an intermediate position in the control room.

Three wires into the limit switches were damaged.

The cable was reformed and the limit switch was replaced.

f'