ML17326A410

Monthly Operating Rept for Nov 1979

ML17326A410
Person / Time
Site:	Cook
Issue date:	12/03/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17326A408	List: ML17326A407 ML17326A410
References
NUDOCS 7912170274
Download: ML17326A410 (10)

Text

OPERATING STATUS OPERA.TIIXC DATAREPORT DOCI'"T iiO. ZL3.15 DATE ~M9 CO~IPLETED BY W.

1 ett T-LEPHOYE ~6-~55-5901

1. Unit!same.

Oonald C.

Cook ovem er

2. Reporiing Period S. Licensed Thermal Power (MNt)t

4. ?i mnePtt R ting (Gross 'i<<!We):

S.

Des!gn ElecaiU~ Rating (Net MWe):

6<<!I!ax!mum Dependabl= Capac?ty (Gross!i!We)t

7. Maxi!num Deoendable Capacity Net MWe):

1979 3250 1080 1044 Notes S.

Ef Changes Occur in Capaci:y Rat'".~p (Items %umber S Throu~4 7) Sine" Last Repor., Give Reasons:

9. Power L vel To YIhich Res+:ct~, IfAny (Piet!IINe):

10. Reasons For Restrict!or, lfAny:

This Month Yr:to-Dat Cumul"tive 5192.1 0

5 10 087 63.8 63.8 7.8 1 I. Hours ln Reporting Period I I...lumber Of Houa Reactor Yeas Critiul 483. 3

13. Re ctor Resene Shutdovn Hovw 8

I4. Hours Generator On-Lhte

15. Unit R~rve Shutdown Hovw

-.='-' '<<

IS. Pet Eiectrical ner~y Cenetat " {!<<IWH) 488

!7

19. Unit Servic Factor "0. Unit Availability Factor

21. Un!t C"pac'.y 'actor (Usin~ II!DCNet) 2". Ur.it Caoacity Factor (Using DER Yet)

64. 3 2S. Unit Forced Outage Rate

33. 8

"- '. Snvtdowns Schedvled Over Hex: o!Ilonths (Type. Date. and Dv=ation of Each]:

463 31,527.5 75.2 75.2 6.5

5. li Shut Do" n At End Of Report Period. Estimated Date oi Startvo:

. -'5. Units ln Test S'a:I.s!Prior to Commercial Operation):

Forecast Achieved IYITJAL CRiTiCALITY lY!TIAL ELECTRICITY CO.'t~lERC!Ai OPERAT10

0

UNITSIIUTDOWNS AND POWER REDUCTIONS RFPORrhIONrll November 1979 DOCKET NO.

50 315

. cCc TELEPIIONE l)atc L

I)

~ V)

Llccnscc I'vent Rcpllft ff 4J~

0 D 2 ~

Cause &, C<)rrcctivc Acth)n lo Pfcvcnt Rccurfcncc 152 791027 243.7 B

1/3 N.A.

CB PUMPXX The Unit was out of 'service at the beginning of the month to perform repair on reactor coolant pump No.

12 to eliminate cause for high pump vibration.

Cause was found to be coupling misalignment.

The Unit re-turned to service at 0345 on 791111.

Reactor power at 100/. at 1803 on 791111.

Total outage time was 350.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

F: Forced S: Schcd<<lcd

(')/77)

Reason:

A.E lulp<<1cnl Fall<<re (Explain)

I).h(aintenrn)ce nr Test C-Ref<<clini, D Ret;ulatofy Restriction I'.Oi)crrltofTfai<<II)ll&. LlccIIsc Exanllnat il)ll F-Administrative G Operational Error (Explain)

I I Other (Explain) hlethod:

I -Manual 2.h(anual Sera<<I.

3-Automat tc Sera)<<.

4 Qlhcf ( Cxpl Jul

)

Exhibit G - Instr<<ctions for Prep)rati))n 1)f Data Entry Sheets I'or Lice<<sec Event Rcport (I.ER) File (NURI.'G-O I 6I )

5

'Lxhibit I - Sa)nc So<<rce

UNITSHUTDOWNS AND POWER RED ONS 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-f>cant reduction in power level (greater than 207o 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 dov:n completely>.

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 signiiicant power reduction.

Report as year. month. and day.

August 14. 1977 would be reported as 770814.

When a shuidown 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 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.

Seif~xplanatory.

When a shutdown extends beyond the end ot a report period, count only the time to the end of the report period and pic'p the ensuing down time in the following report periods.

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

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.

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

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation iN>oie that this difi'ers i'rom the Edison Electric Institute (EEI) definitions ol

-Forced PartiJI Outage" and

-Sche.

duied Partial Outage.-

For these t>.r>n~. I:El uses J el>ange oi'0!>IW as the break p>>int.

F>>r larger power reactors.

SO MW is i>>>> sinall a <<llJllge t>> WJfiant explanallo>>.

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'ccurrence pertaimng 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 (NUREG416l).

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 reportable 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.

COMPONEiNT 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 ftt 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 explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut ~

down or sianificant 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-rehted corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release oi radioactivity or single radiation exposure speciiically associ-ated with the outage which accounts for more than 10 percent of the allowable annual values.

For long textual reports continue narrative on separate paper and ret'>'.rence tlie shutdown or power reduction for tl'.is i>JI'i'Jtive.

RAGE DAILY UNIT POWER LEVEL DOCKET No.

50-'315 UNIT 1

DATE 12-3-79 COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 10 12 13 15 16 1040 1043 1042 1042 1042 18 19 20 22 23 25 26 27 28 29 30 31 1043 1043 1042 1042 1043 1045 1023 1044 1043 1044 1

2 1043 INSTRUCTIONS On this format list the average daily unit power level

',n MWe-Net for each

. day in the reporting month.

Compute to the nearest whole megawatt.

Docket No..

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 81 R.

S.

Lease (616) 465-5901 December 6, 1979 1 of2 MONTHLY OPERATING EXPERIENCES -- NOVEMBER, 1979 Hi hli hts The Unit entered the reporting period in Mode 5 with Reactor Coolant Pump 812 undergoing repairs.

The Unit was started up and power generation commenced

Sunday, November ll, 1979 as detailed in the summary.

Total electrical generation for the month was 505,800 Mwh.

Summar 11/06/79 -- The Reactor Coolant System was filled and pressur-ized to allow manual rotation of the 0'12 Reactor Coolant Pump.

This hand rotation indicated exces-sive runout and the Reactor Coolant System was again drained to 1/2 loop.

11/07/79.Fill and Vent of the Reactor Coolant System com-menced and was completed ll/09/79; 11/09/79 -- Heat-up of the Reactor Coolant System was initiated at 1126 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.28443e-4 months <br /> and entry into Mode 4 was at 1208 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.59644e-4 months <br />.

11/10/79 11/11/79 11/13/79 The Reactor Coolant System entered Mode 3 at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />.

Full temperature was obtained at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

The Reactor was cri.tical at 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br />.

The Main Turbine was rolled at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and paralleled to the system at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br />.

The Unit was loaded to 1005 power by 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br />.

-- The Turbine Driven Auxiliary Feedwater Pump was inoperable at 0527 hours0.0061 days <br />0.146 hours <br />8.713624e-4 weeks <br />2.005235e-4 months <br /> to make repairs to leaking safety valves to the cooling water system.

This pump was again operable at 1252 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.76386e-4 months <br /> ll/15/79.

ll/17/79 --=Unit power was reduced to 855 for testing of Turbine Control'alves.

Total time below 100'/ power was 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.

11/19/79 -- The Turbine Driven Auxiliary Feedwater Pump was inoperable for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> to replace and test the Governor.

Docket No.:

50-315 Unit Name:

D.

C.

Cook Unit Pl Completed By:.

R.

S.

Lease Telephone:

(616) 465-5901 Date:

December 6, 1979 Page:

2 of 2 ll/24/79 -- Unit power was reduced to 85Ã for testing of Turbine Control Valves.

Total time below 100%. power was 5

hours.

11/27/79 -- The Boric Acid Transfer System was inoperable for a 17.3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period for unplugging the Emergency Boration Line.

DOCKET NO.

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

C.

Cook - Unit No.

1 12-13-79 B. A. Svensson 616 465-5901 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE NOVEMBER, 1979 M-1 M-2 M-4 M-5 M-6 CSI-1 Loops 2 and 3 safety injection containment isolation valve, ICM-ill, would not operate.

Investigation revealed condensation in limitorque control box, had caused failure of.,the torque switch.

The motor heater wires were broken.

Repaired broken wires and sealed housing.

Valve operability was verified.

The west centrifugal charging pump mechanical seal-was leaking.

The mechanical seal was replaced and the pump tested.

Pressurizer power operated relief valve, NRV-151, was leaking by.

Replaced the seat ring, plug, stem, all gaskets and the air operator diaphragm.

Valve operability was verified.

Pressurizer power operated relief valve, NRV-152, was leaking by.

Replaced the plug, stem, all gaskets and the air operator diaphragm.

Valve operability was verified.

Pressurizer power operated relief valve, NRV-153, air operator dia-phragm leaked.

Replaced diaphragm and had valve tested.

CVCS holdup tank vent header isolation valve, CS-151, would not close.

Valve bonnet was replaced.

Unit 1 emergency boration line was clogged.

Removed bonnet from CS-484 and purged the line.

Flow was restored.

A resistance thermal device (RTD) on reactor coolant pump No.

2 re-quired replacement after being damaged during disassembly of the motor.

CS I-2 CKI-3 Charging flow control valve, HARV-251, would not open.

The high and low limits of the controller were found misadjusted which prevented operation of the controller in auto, or manual.

The limits were adjusted to the correct values to allow correct valve operation.

Delta T-Tavg Protection Channel I, had previously been producing spikes which required placing the spare RTD of the cold leg into service.

During the Mode 5 operation, the sporadic RTD was removed and replaced with a new Rosemount RTD.

The resistance to voltage converter calibration was completed and the protection channel was returned to normal operation.

DOCKET NO.

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

C.

Cook Unit No.

1 12-13-79 B. A. Svensson 616 465-5901.

2of2 MAJOR SAFETY-RELATED MAINTENANCE NOVEMBER, 1979 Radiation Monitoring System Channel R-2, containment personnel air lock area monitor, failed low.

The cable at the detector was found loose.

The connector was retightened and sealed.

Correct operation of Channel R-2 was verified following resolution of the connector problem.

DCR-610 and DCR-611, ice condenser air handling units'rain contain-ment isolation valves, would not remain open when operated from the control room.

The limit switches on both valves were incorrectly positioned, preventing the control circuit seal-in from operating properly.

The limit switches were adjusted and lubricated.

The valves were functionally tested to verify correct operation.

Protection Set I, Delta T-Tavg Hot Leg RTD, had a leak on the bypass manifold.

The RTD was removed and a spare installed.

The backing ring on the RTD was missing which resu'lted in the leakage.

The re-sistance to voltage converter was calibrated and surveillance test was performed.

Containment isolation valve, ECR-31, would not close.

The solenoid valve would not allow the air pressure to bleed off and close the valve.

The solenoid was replaced and correct valve operation was verified.

Accumulator No. 1, level indication channels, were not indicating the same values.

The transmitters were recalibrated and the in-strument loops placed in service.

Steam generator No. 4, level indicator BLP-141 read 10Ã higher than BLP-140 and BLP-142.

Recalibration of BLP-141 Barton transmitter was attempted, but the transmitter shifted during calibration.

A new transmitter was installed and calibrated.