ML17317B097

Monthly Operating Rept for Mar 1979

ML17317B097
Person / Time
Site:	Cook
Issue date:	04/05/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B095	List: ML17317B094 ML17317B097
References
MOR-790331, NUDOCS 7904180247
Download: ML17317B097 (9)

Text

AVERAGE DAILYUNITPOW" R L:-VEL DOCK:-7 VO UNIT DA1" COMPLETED BY HON+

4-5-79 M.T. Gi 11ett MONm March 1979 DAY AVERAGE DAILYPOWER LEYEL IMWe-iles) 1065 1062 DAY AVERAGE DAILYPOWER LEVEL (MWe-. iet )

1005 1013 10 13 16 1027 1072 1073 1070 1073 1077 1072 845 947 1080 1078 1083 1085 1077 19 20 71 l5 26 2S

'l9 30 1048 1078 1075 1073 1070

, 1029 1080 1080 j io7o I 1074 1067 1078-,

1075 INSTRUCTIONS On this tnr-...at.!is::h averaae ".':y nit pnN'r I::!:n lit~'e Yet'ter.aah r'ay in th repro;:na:ni>ntn. Cut-"u:

tu'ne n arest v'i1cte na a lvat t.

(c)rg I )

>904>80>97

OPERATIC DATAR""PORT DOCKET %0.

co>ieLEVZo sV ~W~ ett TELEPHONE ~~M901 OPERATING STATUS Donald C.

Cook 2

3. Licensed Thermal Power PiNt):

4. Nameplate Rating (Gross liINe):

5. Design EIectri I Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MNe)t

7. Kiaximum Dependable Capac ri (Yet MNe)!

3 391 1,133 1

100 1

118 1

082 Notes S. IfChanges Occur in Capacity Ratings (It ms Number 3 Through 7) Since Last R pors. Give Reasons:

9. Power Level To Nhich Reseictat, IfAny (Net hINe):

10. Reasons For Restrictions, IfAny'his Month Yr.-to-Date Cumuhtive ll. Hours ln Reporting Period

13. Number Of Hours Reactor Nas CHtical

13. Re"ctor Raerve Shutdown Hours

14. Hours Generator On-Line

15. Unit R~rve Shutdown Hotm

16. Gross Thermal Energy Generated (MNH)

I I. Gross EIecmcJ Energy Generated (bINH)

18. Net Electrical Energy Gene! t d (iINH)

19. Unit Servic Factor

30. Urit Availability Factor ZI. Un!t Capacity Factor (Using iiIDCNe()

3". Urit Capacity Factor (Using DER Net)

~. Unit Forced Outage Rate

4. Shutdowns Scheduled Over Next 6 bionths (Type.

744 0

744 0

2 1

2 126.5 0

2,106.6 0

10,920 7,357.

0 6,834.

0 483 455 812 720 785,053 2,256,830 100

97. 5 100 97.

93.2

95. 9

91. 7 2.5 0

Date. and Duction of Each):

6,242,360

83. 9 83.

74.5 73.

5.3 6 944 731 20 049 838

'5. IfShut Down At End Of Report P:iod. Estimated Date of Startup:

'5. Units In Test Sta:us (?nor to Commercial Operation):

Force" st Ac'!levery INITIAL CRITICALITY INITIAL ELECTRICITY CO.'lDIERCIA L OPER ~ TIOY

UNITSIIUTDOlVNS AND PO)VER REDUCTIONS REI'QRT hloNTII March 1979 DOCKET NO.

UNITNAhlE DATE COhlPLETED DY TELEPIIONE 50-316 D.C.Cook-vensson

~

~ ~

Nu.

Date

~e r

m ~rx qp Ll cell sec Evcot Rcpilrt 4

~I/1 o

4l Z7 E r3 O

CJ Cause 8i, (.i)rrcclivc Action Ill Pfcvcol Rccorrcocc 52 53 790310 790331 S

0 S

0 B

B N.A.

N.A.

ZZ ZZZZZZ ZZ ZZZZZZ Reduced reactor to 80Ã to perform initial performance testing at this power level.

Reactor power returned to 100$ 790311.

Reactor power reduced to 555 to per-mit removal of test flow nozzles in the main feed pump turbine condensate drain lines.

I I: Forced S: Schediilcil

('J/77)

Reason:

A-E iuipolent Failure (Explaiii)

II-h(aintcnance or Test C-Rcfuelini; D-Reyilatory Restriction E.Opcrati)f Trainllli,Ec Lli:cosc Lxaollllatii)o I -Adolinislrativc G Opcratiu>>al Error (Explaiii)

II.Other (Explaiii) hlcthod:

I-hlaooal 2 hlaoual Scrain.

3-Ailtoolatic Serillo.

4-Ot lier (Explain)

Exhibit G - Instructions I'or Preparation of Data Lntry Sheets for Licensee Event Report (LI!R)File(N(IRI!G.

OI6I)

Lxhibit I - Saul<<Siluree

SHUTDOWNS AND POWER REDUCTIO 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 20k 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 signiiicant reduction in power for that calendar year.

When a shutdown or significant power

'eduction 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.

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 signittcant 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 signittcant 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 inciude those required to be initiated, by no later than the weekend following discovery of an oii-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.

Seifwxplanatory.

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 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.

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

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Caieaorize by number designation Nnie thai this difters irnm the Edison Electric institute

{EEI) definitions ot'Forced Partial Outage-and

-Sche-duled Partial Outage."

Fiir these tern>>. Ef1 uses a change ot'0 4IW as the break point.

Fnr larger pnv er reactors. ~0 MW is tiin small a <<hange tn warrant explanaiii>>i.

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.) Ifthe outage or power r'eduction 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 (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 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 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 amplify or expiain 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. 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 reduction includingan identification of the critical path activity and a report of any single release of radioactivity nr 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 tlie shutdown or power reduction inr tliis liarfJflve.

(9/7

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

50-316 D.

C.

Cook Unit O'Zi R.

S.

Lease (616) 465-5901 April 12, 1979 MONTHLY,OPERATING EXPERIENCES -- MARCH, 1979 Hi hl i hts This Unit operated at full Reactor power the entire period except as noted in the summary;-

Total electrical generation for the month was 812,720 MWH.

Summar 03/02/79 -- Power was reduced to 90% for testing of Turbine valves.

Total time below lOOX power was 9.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

03/03/79--

03/07/79--

The West ESW Pump 'seized iand failed at 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br />.

The pump was renewed and returned to service at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> on 3/5/79.

0 The first Initial performance Test was conducted on this date at 100/ power.

The testing involves about 140 pressure measurements, 160 temperature measure-

ments, power measurements and radioactive sodium tracer for moisture determinations.

Test duration was 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

03/09/79--

03/10/79--

03/11/79--

Loading was reduced to 915 for testing of Turbine valves.

Loading was further reduced to:80/ by 0100,3/10/79 and held at this point for Initial Performance 'Testing.

J

/i Initial 'Performance 'Testing performed at 80/ power.

/"'I n

Initial l Performance Testing performed at 80/ power..

Power was returned to 1005 between the hours of 1210 and 1545.

03/12/79--

03/13/79--

03/16/79--

Initial ~Performance <Testing per formed at 100%%d power.

Initial Performance Testing performed at 100% power with 2.5 inches Hg Turbine backpressure.

Power was reduced to 925 for testing of Turbine valves.

Total time below 100K power was 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The "A" set of low pressure heaters was removed from service at 2204 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.38622e-4 months <br /> to remove a condensate flow nozzle 'that had-.'een used for the ~I,'nitial ~Performance ~Testing. "

T'I

)I" v

I I(

I > )

< 'i L

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 5'2 R. S.-Lease (616) 465-5901 April 12, 1979 Two (2) 03/16/79 During the heater outage the 4-A heater was found to (Cont.)

have numerous tube leaks.

Tube leaks were repaired and the set of heaters was returned to service at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> 3/18/79.

03/18/79--

03/19/79--

,The discharge valve of 823,CWP failed and slammed.shut at 0330 hour0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> s.

This is a butterfly-type valve and the drive tube between the valve operator and the valve failed.

Repairs were made and,the valve and pump were returned to service at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br /> 3/23/79.

The Southwest set of reheater coils were removed from service at 1708 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.49894e-4 months <br /> due to excessive tube leakage.

The unit is now operating with only the 2 "N" sets of reheater coils in service.

03/23/79 --

Power was reduced to 93/ for testing of Turbine valves.

Total time below lOOX power was 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

03/24/79--

03/31/79--

The "B" set of low pressure heaters was out of service for a 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> period to remove a condensate flow nozzle that had been used in the (Initial ~Performance

,Testing.

Power was reduced to 944 power starting at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> for, testing of Turbine valves.

Power was further reduced to 55/.power 'to remove the East Hain Feed Pump from service.

The feed pump was removed from service to remove a..drain flow nozzle that had been used in the Initial~ Performance (Testing.

~

~

(r, f

DOCKET NO.

50 - 316 UNIT NAME

~brook - Unit No.

2 DATE 4-13-79 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1979 M-3'&I-1 Auxiliary feedwater valve to 81 steam generator FM0-212, would not close.

Tightened a loose connection on terminal in the hot shutdown panel and had valve tested.

While attempting to start the west ESW pump, the breaker tripped and pump was found to be bound.

Rebuilt pump using new bowl assembly,

bearings, packing and grease seal.

Had pump retested.

Breaker for reciprocating charging pump tripped when starting pump.

Replaced solid state trip device and inspected breaker.

Tested satisfactorily.

One channel orr the containment dew point recorder failed low.

The operational amplifier had failed and was replaced.

The recorder was calibrated and returned to service.

C&I-2 Stop valve C of the Main turbine was in the open position with the valve position status light and annunciator indicating the valve was in the closed position.

The Train B limit switch was replaced at 0915 on 3-3-79.

The cable cannot be connected until the stop valve can be retested.

C&I-3 C&I-4 C&I-5 C&I-6 The rod position indication system for rod D-4, indicated 212 steps with the demand counter indicating 201 steps.

The primary and secondary LVDT voltages were measured and verified correct.

The signal level output of the signal conditioning module was also measured and verified to be correct.

The panel indication meter was adjusted for correct'indication.

A pyroalarm detector in the reactor cable tunnel quadrant 4, alarmed and could not be reset.

The detector was removed, cleaned and the sensitivity adjusted.

Radiation monitoring system channel R-25 filter paper drive failed.

The paper drive motor was removed and a spare motor installed.

The paper takeup tension was adjusted for the correct loading.

An alarm on circuit 27 of the Containment Fire Detection system was received.

A loose connection was found on a terminal'trip for the alarm card.

The connection was tightened apd the alarm cleared.