ML17317A743

Monthly Oper Rept for Oct 1978

ML17317A743
Person / Time
Site:	Cook
Issue date:	11/01/1978
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A742	List: ML17317A741 ML17317A743
References
NUDOCS 7811210391
Download: ML17317A743 (16)

Text

AVERAGE DAlLYUNITPOWER LEVEL DOCV=-T NO.

11-1-78 CPMPLET~D IIY

>> <. *G~>><<t T>>LEPHPNE 616-465-5901 October 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

I 1 034 DAY AVERAGE DAlLYPOWER LEVEL (MWe.Net) 1,037 17 10 IS l5 l6 1,029 1 033 1,034 1,035 735 817 1,035 037 1,032 1,036 1,037 1,033 1 038 1 040 1,040 18 l9 2l 24 85 26 27 2S o9 30 Sl 1,033 1 037 1 040 1,044 1,041 1 042 1,039 1,045 225 681 1,039 1,043 INSTRUCTIONS On this format. list the averaSe cail( unit oiiiver lei'e! tn Mt'et ior each ciao in the rePurttnpmiinth. Ci>mpute t~t'he nearest u'hole meSaivat t.

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OPERATING DATA REPORT DOCKET NO. 243;tr O~Ti ~>>-

COMPLETED BY TELEPHONE M6~~01 OPERATING STATUS Urtt Name Donald C. Cook 1

2. Reporting Period

3. Licensed Thermal Power (MWt):

4.. Nameplate Rating (Gross MWe):

5. Design E)ectri& R"ting (Net MWe):

6. ifaximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe)t 3,250 1 089 1 080 1 04 Notes

8. IfChanges Occur in Capacity Ratings (Items Number 3 Throu~@ 7) Since Last Report. Give Reasons:

9, Power Level To Which Restricted, IfAny (Net MWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to-Date Cumulative 745 7 296 5,289.2 5,159.7 15 793 815 344

70. 7 70.7 65.8 65.2 4.2 Il. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 731. 6

13. Reactor Reserve Shutdown Hours 0

14. Hours Generator On-Line 729.9

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (AWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

22. Unit Capacity Factor (Using DER Net)

93. 1

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):

33,600 25 9U..9 463 25 129.5 321 67,350 008 21,968,120 21 063 140

77. 7 77.7 67.7 63.5 6.2

25. IfShut Down At End Of Report Period. Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY CO MIDIERCIAL OP" RATION

(')f77 )

L

UNITSIIUTI)OWNS ANI)POlUER REDUCTIONS REI'ORT hlONTII October, 1978 l)OCKETNO.

ll=l cohIPLETEI) Ity B.A. Svensson Nil.

l)atc ri Vlrj PJ Llccnscc Event Rcport 4f CQ EJ ILI Vlill'r e vl p 0 p p Eu p

Cause

81. Corrective Action til Prevcot Rcenrrcoee

.1 37

]38 781006 F

78]028 F

0 15.1 H

1 A

1 N/A 78-060/03L-0 ZZ ZZZZZZ CA VALYEX Reactor power reduced to 65K to aid in cleanup of feedwater cycle con-tamination due to acid leakage from makeup plant.

Reactor power re-turned to 1005.781007.

Unit removed from service and placed in Hot Standby due to unidentified reactor coolant system leakage in excess of 1

gpm.

Leak found to be packing leak on pressurizer safety valve loop seal drain valve.

Leak was isolated and Unit returned to service.

1005 reactor power reached 781029.

I': Forced S: Scheilulcil (i>/77)

Reason:

A.I:iluipotcnt Failure (Explain)

II hlainlcnaoce or Tcsl C-Rcfoclhtg D Regltlatory Restrietiuo I.Operator Training lli License Iixatnination F.Adnlioistrativc (I Opeiatiullal LIrut (I:xpl Jul)

I I Other (I.xplain) 3 hlcthud:

I-hlaooal 2 WJooal Seiatn.

3.Antinna lie Scranl.

4.0tltcr (Explain)

Exhibit G - Instructions for Preparation i)fl)at J Lntry Sheets for l.leensee I.vent Rcpilrt (I.I'.R) File (NURI!O-OI 6I )

'(exhibit I

~ Salne Sin<<ee

UllITSHUTDOWNS AlID POWER REDU ONS INSTRUCTIONS This, report should. describe all plant shutdowns during the report period.

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

Eacn signi-

."ic nt reduction in power level (gr ater than 20% reduction in~averai3e daily power level 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,ieven 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 coiumn shouM be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

in accordance with the tab!

appearing on the report iorm.

Ifcategory 4 must be used. supply brief comments.

LICENSEE EVENT REPORT =.

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

Enter the iirst iour paris (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 (NUREG416l).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be reauired to ascertain whether or not a reportable occurrence was involv d.) Ifthe outage or power reduction will not result in a reportable occurrence.

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

NUMBER,Thiswol'umnishauld 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 Jl shutdowns or significant power reductions are reported.

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

SYSTE.'iI 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 desiana-ted XX. The code ZZ should be used for those events where a system is not applicable.

C.

If a chain of failures occurs, the first component to mal-function should be listed. The seauence 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 ut any existing code should be de.

signated XKO<XX. The code ZZZZZZ should be used for events where a

component designation is not apolicable.

DURATION.

Seif~xpianatory.

When a shutdown extends beyond the end oi a report period, count only the time to the end ui'the r port 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 faciTitate 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 pe ilad.

CAUSE & CORRECTIVE ACTION TO PREYED RECUR-RENCE.

Use the column in a narrative fashion to ampiify or explain the circumstanc s oi 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 oluinn should also be used for a description of the major safetv-rehted corrective maintenance performed during the outage or power reduction including an identification of the critical path ac:iiity and a report of any single reiease oi radioactivity vr single radiation exposure specitically associ-ated with the outage which accounts ior more than 10 percent oi the allowaole annual values.

For long.textua! reports continue narrative on separate paper and reierence the shutdown or power reduciivn ivi tlni narrative.

REASON.

" Categorize by 'letter designation in accordance with ihe table appearing on the report form. Ifcategory H must he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation 14(ite -that 'this diiiers.i'rom the Edison Ele tric lnsiituie (EEI) detiniiions.ot'; -Forced Partial Outage-and

-Sche-duled Partial Outage."

For these tern>>. EEl uses a cliange oi

.0 MW as the break point.

Fvr larger purr reactors. ~0 MW is iv<> >null a change io warrant explanatlvll.

DATE.

This column should indicate the date oi the start of each shutdown or significant power reducuon.

Report month. and dav.

August 14. 1~77 wo~ld be ~~po~t~d COMPONENT CODE.

Select ihe mast appropriate c~mpo~~~t as 770814.

When a shutdown or significant po~er reduction I'rom Exhibit I - instrucuons for Preparation oi Data Entry beglnsinonereportperiodandends in another, an entry should Sheets for Licensee Eve!it Report (LER) File(NUREG+161).

be made Sor.both. report.'periods to:-be sure ail.shutdowns

'using the followingcritieria.',

or significant;powerveductianmezeported-..:;

a;;:..:- -. -,

• '. Ifa component failed, use the component directly involved.

TYPE:",'Use."F:.,=or.:"S":.to indicate either"Forced" or "Sche.'uled."

respecuvely, for each shutdown or significant po~er B. If not a component failure. use the related component:

reduction.

Forced shutdowns inciude those required ta be e.g..

wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component.

of an oif-normal condition. It is recognized that some judg-me'nt 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.

e Docket Unit Name:

Date:

Completed By:

Telephone:

50-315 D.

C.

Cook Unit ¹1 November 14, 1978 R.

S. Keith (616) 465-5901 OPERATING EXPERIENCE -- OCTOBER 1978 Hi hli hts Unit 1 was on line 734 hours0.0085 days <br />0.204 hours <br />0.00121 weeks <br />2.79287e-4 months <br /> and 55 minutes out of a possible 745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />.

Summar 10/01/78 The Unit entered this reporting period at 100Ã power.

10/02/78 The Turbine Driven Auxiliary Feed Pump failed to meet Surveillance Test requirements for speed and was declared inoperable.

10/03/78--

10/04/78--

The Turbine Driven Auxiliary Feed Pump was declared opera-ble at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />.

The East Containment Spray Pump was made inoperable at 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br /> to repair CTS-105E which had a stripped yoke bushing.

The Turbine Driven Auxiliary Feed Pump,,again failed. to reach operating speed on the functional test.

The Governor was replaced and the pump was declared operable't 2052 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.80786e-4 months <br />.

10/06/78 The East CTS Pump was declared operable at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

At 0229 hours0.00265 days <br />0.0636 hours <br />3.786376e-4 weeks <br />8.71345e-5 months <br /> started reducing power to 75% because of high conductivity in the Steam Generators.

75% power was reached at 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br />.

At 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br /> started reducing power to 65K to assist in reducing steam generator conduc-tivities.

65K power was reached at 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br />.

RPI for control rod K-12 had greater than a

12 step devia-tion between 1930 and 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br />.

10/07/78-- At 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> steam generator conductivities had reduced and make up water capacity had reached a condition where the Unit could be returned to full power.

The Unit was at 100K power at 1802 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.85661e-4 months <br />.

10/10/78 The North half of "A" Condenser was isolated to inspect for tube leaks.

3 tubes were plugged.

10/11/78 Radiation Monitors R-31 and R-32 were removed from service because of a failed pump motor.

E I

Docket No.:

Unit Name:

Date:

Completed By:

Telephone:

Page:

50-315 D.

C.

Cook Unit ¹1 November 14, 1978 R.

S. Keith (616) 465-5901 (2) 10/12/78 Radiation Monitors R-31 and R-32 were returned to service (cont) at 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br />.

10/13/78 At 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />, while regenerating the North Mixed Bed Demineralizer, there was a slight carry over to the Conden-sate system which caused steam generator conductivity to increase.

10/22/78 Radiation Monitors R-31 and R-32 were declared inoperable at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> because of a pump failure.

10/23/78 Radiation Monitors R-31 and R-32 were declared operable at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />.

Pressurizer Level Channel NLP-153 was declared inoperable at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> when it deviated by greater than 4X from the other two channels.

10/24/78 Pressurizer Level Channel NLP-153 was declared operable at 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />.

10/28/78 The Unit was removed from service at 0818 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br /> because unidentified Reactor Coolant System leakage exceeded 1

GPM.

After the Unit was tripped a packing leak on a pressurizer safety valve loop seal line was found.

The v'alve was closed and the leakage stopped.

The Reactor was critical at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> when the Generator was paralleled with the system at 2323 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.839015e-4 months <br />.

10/31/78 The Unit is operating at 100Ã power.

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DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE MAJOR SAFETY-RELATED MAINTENANCE 50 - 315 D. C.

COOK - UNIT NO.

1 11-14-78 B. A. Svensson 616 465-5901

OCTOBER, 1978 M-1 M-3 M-4 M-5 C8(I-1 East CTS pump test line isolation valve, CTS-105E yoke bushing came loose from the yoke.

Valve was disassembled and yoke bushing was re-placed.

The governor on the turbine driven auxiliary feed pump was sticking causing problems with RPM control.

Replaced governor with new one and had operational test performed.

The pump motor for radiation monitor R-31 and R-32 failed.

Replaced motor and had monitors functionally tested.

No.

2 boric acid transfer pump failed to pass performance test.

Dis-assembled pump, adjusted impeller clearance and reassembled pump.

After

repair, performance tests met Technical Specification requirements.

No.

1 boric acid transfer pump discharge valve to boric acid filter, CS-416-1 had a ruptured diaphragm.

Replaced diaphragm.

Engineered safeguards feature ventilation fan, HV-AES-1 bearings were running hot.

Inspected and repacked inboard and outboard bearings.

Functionally tested.

VCR-ll, glycol supply isolation valve in containment failed to the closed position.

Condensation from surrounding pipes had saturated the terminal strip and control cable.

The terminal strip was replaced with a spare.

The correct valve operation and closure time response was verified.

CLI-2 CSI-3 C8(I-4 SG-17, ice condenser temperature recorder would not print and would also skip points.

The recorders clutch and servo motor required re-placement.

Pressurizer leveI protection channel III NLP-153, indication increased 9%.

The transmitters reference leg was flushed with demineralized water, and pressurized with a hydropump to remove the gas buildup within the piping.

NLP-153 indication returned to within specification.

MPP-230, steam generator No.

3 pressure indication failed low and did not produce an alarm.

The panel indicator was tested and the leads to the indicator were found to have a short circuit condition.

The wiring problem was corrected and the indication returned to normal.

o

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE MAJOR SAFETY-RELATED MAINTENANCE

OCTOBER, 1978 50 - 315 D. C.

COOK - UNIT NO.

1 11-14-78 B. A. Svensson 616 465-5901 (PI-412, the boric acid transfer pump No.

2 discharge pressure

gauge, would not indicate pressure.

The gauge was removed and inspected.

A spare gauge was installed with a gauge saver and a diaphragm.

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Mr. E. E. Fitzpatrick Indiana Michigan Power Company CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street

Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.

Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.

W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0.

Box 30195 Lansing, Michigan 48909 0

Donald C. Cook Nuclear Plant Mr. S. Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43215

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