ML17318A764

Monthly Operating Rept for Apr 1980

ML17318A764
Person / Time
Site:	Cook
Issue date:	05/02/1980
From:	Gillett W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17318A763	List: ML17318A762 ML17318A764
References
NUDOCS 8005200670
Download: ML17318A764 (11)

Text

~ i OPEC'xiiiG DATAREPORT

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8o 052 o o @go

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DOCK"-7 )NO.

DATE CO!iIPLETED SY TELEPHO4" 50-315

~:80 W. T. Gillett

-4

-590$

Oo= w<T>~G ST.'Uc Oonald C.

Cook ilot s

1. Unit ilatne'.

A ril S. Iic nsedThe.

...alPowe:(IIINt):

4o

~ I tneolate R ting (GsoA atIWe)'.

Desi@1 EIecai&~ Rating (Net M>Ve):

6. Mwtnunt Dependable Capacity (Gross hiKe):

7. Niaxirnutn Dep"~dabie Capacit,Net Mme}t 32 1089 1054 0 0 S. IfChanges Occur in Capac.'.y Rati,gs (ltetns Numb=." g Through 7).Since LastR por:. Give Reasons:

9. Power L=vei To elhi"4 Rese:ct~, IfAny (Yet MKe):

IO. Reasons For Rest-'etio', I'ny:

This bionth Yr.-to-Dat.

Curnulatlve 2 903 2,489.4 0

2 481.2 0

7 813 148 2,596,960

,506, 9

85.5 85.5 82.7

81. 9 14.5

11. Hou=s In Reporting Period 719

12. Nm"..ber Of Houa Reactor Yeas C;:tiM 06.6

13. Re"ctor R serve Shutdovvn Hou=

14. Houw Generator On-Lhte 000. 6 IS. Unit R~ve Shutdown Ho"a

.66

,660 IS. Yet Electri I Ene:gy Gener" t " { DVH)

19. Unit Setvic" Factor 97.4

0. Un:t Avaihbiliv. Factor

'1. Unit Capaci'.y Factor (Using li!DC Net)

.4.

Shutdowns Scheduled Over Yeast 5 ~months lType. Date. and Duration of Each):

May 30, 1980 - July 20,1980 Refuelin Outa e

35 463 96 34 6

321 31 754 300 30,503,508 77.7 77.7 68.1 63.4 7.

"S l'S't-Down At Fnd Of Re-ort P riod. Es!itncted Date ot Startuo:

. 5. Units ln Test S;a." s IP6rior to Commercial 0".-.tionI:

Forec" st Achieved INITIALCRITICALITY I

0 6

+f6

~.V CO6 6~6 yP 6,

~

AAGE DAILY UNIT POMER LEVEL 0 DOCKET"NO.'50-315 UNIT DATE 5-1-80 COt1PLETED BY W. T.

Gillett TELEPHONE 616-465-5901 HONTH April DAY AVERAGE DAILY POWER LEVEL 1046 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 10 12 13 15 16 1047 1046 1045 1027 1044 1042 178 410 873 1041 1023 1045 1045 1046 18 19 20 21 22 23 24 25 26 27 28 29.

30 31 10 5

1035 1032 1045 1044 1044 1045 1043 1047 1047 1046 1048 INSTRUCTIONS On this format list the average daily unit power level in NWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

UNITSIIUTDOWNS AND POWER REDUCTIONS PORTMONTII April, 1980 DOCKET NO.

TlTm COMPLETED DY TFLEPIIONF 616 465-5901 a

N)).

Date r)

Vl

~lo I

J

~ V)

Llccnscc Event Rcpl)ft Jr o ~

r)

O Cause A, Cl)rrcctivc Act)on to Prevent Rccurrcncc 159 800408 18.4 H

3 N.A.

ZZ ZZZZZZ The Unit tripped from 100%%d as a re-sult of a lightning strike near the underground control cables between the plant and the switchyards.

The generator output breakers opened causing load rejection.

This in turn caused steam generator water levels to shrink below the low-low level trip point which caused the reactor trip.

Unit returned to service the same day., Reactor power limited to

<505 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to aFlux limits.

100%%d power reached 800410.

I': Forced S: Sched<<le)I

('>/77)

Rcasl)n:

A-Erluipn)cnt Failure (Explain)

I) Maintcilanec or Test C-Rcfuclinl, D Rct,ulatnry Restriction li-Operator Traininlih. Uccnsc ExJnlinalion F-Administrative G.Operational L'rror (I'.xplain)

I I Other (ExplJhl)

Method:

I -Man))al 2.Manual Scraln.

3-Automatic Scr;un.

0-Other (Explai>>)

Exhibit G - Instructions for Preparatiml of Data Lntry Shccts for Licensee Event Rcport (LI!R)File (NUREG-OI6I) 5

'Lxhibit I - Salnc Source

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 20fo 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 l. 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 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 signiricant 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 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 fouowing 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.

Self~xplanatory.

When a shutdown extends beyond the end oi a report period, count only the time to the end ot the report period and-pick up the ensuing down time in'he following report periods.

Report duration of outages rounded to the nearest tenth ofan hour to faciTitate summation.

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

REASON.

Categt>rize by letter designation in accordance with the table appearing on the report t'orm. Ifcategory H must be used. supply brie t'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation l.'v'ote that this differs i'rom the Edison Electric Institute (EEI) definitions ot'Forced Partial Outage" and

-Sche.

duied Partial Outage.-

F>>r these tern>>. hf1 uses a cltange ot'.0!>IW as the break 1>>>int.

F<>r larger po>>er reactors. SO MW is I>>(> si>>all a change ii> warrani explanation.

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 reduction will not result in a repor'table occurrence.

the positive indication of this lack of correlation should be noted as not applicable (N/A).

SYSTFM 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.

CO>>IPONENT 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. Ifa component failed, use the component directly involved.

B. If not a component failure, use the reiated 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 app)icable.

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 ~

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 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 an>l ret'erence tlie shutdown or power reduction ior iliis llaffatlve (9/>>

DocI No.:

Uni arne:

Completed By; Telephone:

Date:

Page:

50-315 D..C.

Cook Unit 5'1 C.

E. Murphy (616) 465-5901 May 6, 1980 1of 3 MONTHLY OPERATING ACTIVITIES -- APRIL 1980 Hi hli hts The Unit operated at 100Ã power the entire reporting period except as detailed in the Summary.

There was one outage of the Reactor and"~Turbine Generator Unit during the reporting period.

This is also detailed in the Summary.

Total, electrical generation for the month was 802,710 Mwh.

Summary 4/5/80 Power was reduced to 90% for testing of Turbine Valves.

Total time below 100'4 was 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4/6/80 4/7/80 4/8/80 The Control Rod Urgent Failure Alarm sounded.

No cause for the alarm could be identified.

The Control Rod System was reset, after a

2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period, and the Control Rods were exercised to prove operability.

The North half of "A" Condenser was out of service for a 5.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period for checking of tube leaks.

The Unit and Reactor tripped from 100K at 0403 as a

result of a lightning strike near the underground control cables between the plant and the switch-yard.

Generator output Breakers K and K-1 opened causing load rejection.

This in turn caused all Steam Generators to shrink below the low-low level trip point and the Reactor was tripped from the No.

3 Steam Generator.

Reactor Coolant Pumps tripped from low frequency.

However, automatic transfer of the other Auxiliaries was successful.

4/9/80 4/10/80 The Reactor was returned to Criticality at 2026, and the Unit paralleled to the System at 2227.

The Unit was loaded to 49K Power at 1200.

Due, to Core conditions, Axial Flux could not be maintained within the target band during start-up.

Time outside the band was 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 3 minutes.

This required holding Reactor. Power below 505 for at least 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.

Loading of the Unit comoenced at 0343, today and 1005 Power was reached at 1049.

Docl~ No.:

Uni~iame:

Completed By:

- Telephone:

Date:

Page:

50-315

,D.,C.

Cook Unit ¹1

.C.,E.

Murphy (616) 465-5901 May 6, 1980 2of3 4/11/80 4/12/80 Unit power was reduced to 904 at 2205, for testing of Turbine Valves.

Unit power was increased to 92/ at 0202.

Power was held at this point while trouble shooting the tur-bine control valve test circuit to determine cause for the test circuit not performing as designed at 100/ power.

The investigation is being continued.

Power was returned to 1005 between the hours of 0512 and 0643.

4/15/80 4/16/80 The Containment Recirculation Fan 1-HB-CEO-1 was inoperable for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period while Power Cable terminations were replaced.

The Emergency Safeguard Fan 1-HV-AES-2 was inoperable for a 4.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period while Power Cable terminations were replaced.

Power was reduced to 951. by an inadvertent Boric Acid injection at 0103.

Power was returned to 1005 by 0225.

The Control Room Ventilation 1-HV-HCRA North 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 while Power Cable terminations were replaced.

4/17/80 4/18/80 4/19/80 The Hydrogen Recombiner No.

2 was inoperable for a 6.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period while Power Cable terminations were replaced.

"C" North Condenser half. was out of service for 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to check for leaks.

Containment Radiation Monitor R-ll failed at 1125.

The detector tube was replaced and the Monitor de-clared operable at 1110, Sunday the 20th.

Power was reduced to 90K at 2300 for the purpose of testing the Main Turbine Control Valves.

During this time Unit 2 tripped and the Valve test was postponed.

Power was returned to 1005 at 0335.

The East Centrifugal Charging Pump was inoperable for 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> to change oil.

The Plant Meteorological Instruments were inoperable between the hours of 1433 and 1450.

Docket ~:

Unit N~:

Completed By; Telephone:

Date:

Page:

50-315 D.,C.

Cook Unit.¹1 C.

E, Murphy (616) 465-5901 May 6, 1980 3of 3

4/20/80 -- Power was again reduced to 90K at 0410 and the Turbine Control Valves tested.

The Unit was returned to 100%

power at 0933.

IRV-252, BIT Recirculation Outlet Valve failed closed at 0310.

It was operable at 0445.

A spurious operation of the Turbine Building Wall Deluge System occurred.

No cause could be found.

4/21/80 -- HV-AFX-1, Spent Fuel Pit Exhaust Fan was declared inoperable when it failed a performance test due to low flow.

4/22/80 The ¹1 Boric Acid Transfer Pump was removed from service to replace the pump seal.

4/25/80 --,The ¹1 Boric Acid Transfer Pump was returned to service.

4/28/80--

"C" South Condenser was removed from service for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> for leak testing and repairs.

Condenser s removed from service for leak testing and repairs were as follows:

"C" North Condenser for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> "C" South Condenser for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> "B" North Condenser for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> "B" South Condenser, for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4/29/80 -- Condensers removed from service for leak testing and repairs were as follows:

"A" North Condenser for 3 '

hours "A" South Condenser, for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> The Make-up Plant was out of service for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to make tie connections for the Demineralized Water Header.

4/30/80 -- HV-AFX-1 was declared operable.

l

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 D.

C.

Cook - Unit No.

1 5-13-80 B. A. Svensson 616 465-5901 1 of MAJOR SAFETY-RELATED MAINTENANCE APRIL,,1980 M-2 C&I-1 The cable from 600 VAC circuit breaker llB1 to motor control center 1-ABD-B 8504R1 was damaged when stepped on by contractor personnel.

Replaced the cable and performed applicable electrical checks.

The sample pump for radiation monitors R-31 and R-32 was running noisy.

Replaced the pump with a new one.

The reciprocating charging pump was leaking.

Replaced the plungers, stuffing boxes,

packing, glands and all adapters on ¹2 and ¹4 cyl-inders.

Functionally tested the pump.

The ¹1 boric acid transfer pump mechanical seal was leaking.

Replaced mechanical

seal, bearings, shaft, impeller, gaskets and o-rings.

Ver-ified proper pump operation.

An urgent failure alarm on the rod control system was received.

The alarm originated from the phase failure detector on the movable gripper group 1, control bank D.

The cause of the alarm could not be deter-mined.

The alarm was reset and remained cleared.

CRI-2 CKI-3 CKI-4 Several analog rod position indication channels were indicating incor-rect positions.

Channels C9, J3, Jll, B8, D8, M8, H6, F8, F2, B10, K14, B6, F14, K2, Nll, L13, L3 and N3 were recalibrated to provide proper indication.

Primary water to boric acid blender control valve, HARV-412, would not open completely.

The solenoid valve supplying air to the valve was leaking through the vent.

The solenoid valve was replaced with a spare.

IRV-252, boron injection tank recirculation to the boric acid storage tank, would not open from the control room.

The valve's stem was frozen, in, position.

The stem was freed with induced vibration and the valve opened.

The valve was cycled several times to ensure operability.

The valve will-be examined during the upcoming'outage.

~ Ly l

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