Text

Monthly Oper Rept for Nov 1978
	ML17317A813
Person / Time
Site:	Cook
Issue date:	12/04/1978
From:	Gillett W; INDIANA MICHIGAN POWER CO.
To:	;
Shared Package
ML17317A812	List: ML17317A811; ML17317A813;
References
	NUDOCS 7812200205
	Download: ML17317A813 (17)
	v • d • e

AVERAGE DAILYUNITPOWER I VEL DOCV~- ~O.

UNIT 12-4-78 COMPLETED IIY TELEPHONE 616 465-5901 MONm DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

I 837 639 723 579 545 565 770 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 18 10 I3 724

)5 27 o9 18 525 368 885 1,023.

909 15 I6 31 INSTRUCT1ONS Qn this toraat. list th aver g daily ut.it oi>ii'er Ieve! tn M~~'e.:let f'r each day in the r purttnz tniinth. Ciunpute tu'he near st whole rnegaivat t.

VSZ22OO205 (c)rgb)

OPERATING DATAREPORT OPERATING STATUS

1. Unit.Name'On>ld C. ~k 2

2. Reporting Period:

~VetnbeX'978

3. Licensed Thermal Power (hWt):

4. Nameplate Rating (Gross hJWe):

5. Design Electrical Rating (Net hJNe):

6. hlaximum Dependable Capacity (Gross hive):

7. hlaximum Dependable Capacity (Net MWe):

1,118 Notes DOCKET NO.

DATE ~~

COhJPLETED BY 3$ '~i1lett TELEPHONE 3~~901 Jf Changes Occur in Capacity Ratings (Items Number 3 Throi:="h 7) Since Last Report. Give Reasons:

9. Power Level To which Restricted, IfAny (Net hJIVe):

10. Reasons For Restrictions, IfAny'his Mort Yr..to-Date Cumulative

11. Hours In Reporting Penod

12. Number Of Hours Reactor 'Was Critical 13, Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (KDVH)

17. Gross Electrical Energy Generat d (hJ>VH)

18. Net Electrical Energy Generated (ihllVH)

19. Unit Service Factor

20. Unit AvailabilityFactor 2J. Unit Capacity Factor (Using hJDC Net)

22. Unit Capacity Factor (Usin~ DER Net)

~D. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 hlonth 720 355 0

323.6 0

848 234 8,016 4,486. 7 0

0 8 016 4,486.7 3 983.6 250 370 238,358 3 165 820 3 i165 g 820 3 022 104 3 022 104

72. 6 72.6 58.6 8.7 72.6 72.6

58. 6

57. 7 8.7

44. 9 30.6 30.1 3.3 s {Type. Date. and D'ion of Each):

25. Jf Shut Down At End Of Report Period. Estimated Date of Sta:: p:

26. Units In Test Status {Priorto Commercial Operation):

INITIALCRITICALITY INITIALELECTRICITY COhthIERCIAL OPERATION Forecast 3~1(78 3~15~78 6/1/78 Achieved

~31~078

'3~278

. 7/1/78

{'>/77I

I UNITSIIUTDO1YNS ANI)POIVEI( REDUCTIONS DOCKET NO.

UNITNAhlE 2

REPORT hlONTIINovember, 1978 I

I PAGE 1

OF 2 N<l.

Date

<r~

<) ~

l)

~ <I) g Lice>>scc Event Rcporl 0 IA o

o

<)

Q O

E~

O Cause & Corlcclivc Aetio>> lo Prevent Rcc>>rrcncc 39 781101 F

40 781104 F

41 781109 S

0 385.2 N/A N/A N/A HH HH ZZ HTEXCH HTEXCH ZZZZZZ Reactor power reduced to 75% to re-move

>>B>> H.P. Heater String from service to repair heater tube leaks.

Power reduction continued to 60% to permit removal of Mest Hain Feed Pump from service to repair leak.

Power increased to 805 781103.

Reactor power reduced to 60K to re-move "A>> L.P. Heater String from service to repair heater tube leak.

Power increased to 80K 781106.

Unit removed from service to perform modifications to Hoisture Separator Reheaters.

Reactor coolant system brought to cold shutdown.

Unit re-turned to service 781126.

Power ascension to 100Ã terminated and power returned to 75K to remove

>>A" H.P. Heater String from service for I': Force>:

A-E I>>)pole>>i Faiillre (Explai>>)

li hlai>>lcnancc of Tcsl

('-Rcfucli>>I, D Iles>>iatoly Rcslrlclio>>

I:-Operator Traini>>II& Lice>>sc Exaolinalion I"Allnolllsllallvc C Opcrallo>>al LllorII:xplaol)

II'Olllcf(I'xplai>>)

hicthod:

I -hla>>ual

'2.hia>>ual Sera>>l.

)3-AlllonlalicScraln.

4.0tllcr (Explain) suspec e

u e

ea 4

Exllibit C - Instructions for Preparalio>> ol')ata I:>>tly Sllcels ior l.icc>>see Evcot Rcport II.I!lh)Fili INURI:C-OI C) I )

I:xllibitI - Sa>>le So>>lce

UNITSHUTDOWNS AND POWER REDU S

INSTRUCTIO>IS This report should describe all plant shutdowns during the report period.

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

Each signi ~

ficant reduction in power levei (greater than

>0% reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completely1.

For such reductions in power level, the duration should be lisied as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should expLin.

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 reductionin power for that calendar year.

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

an enuy should be made for both report periods to be sure Jl shutdowns or sianificant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber should be assianed to each entry.

DATE.

This column should indicate the date oi the start of each shutdown or signirtcant power reduction.

Report as year. month. and day.

August 14. 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 signirtcant 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 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 ofthe conaition for which corrective action was taken.

DURATION.

Seif~xplanatory.

When a shutdown extends beyond the end oi a report period, count only the time to the end oi 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 facilitate summation.

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

REASON.

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

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number desianation INote that this dift'ers irom the Edison Electric Institute (EEI) deiinitions ot

-Forced Partial Outaae" and

-Sche.

duied Partial Outage.-

F>>r these term~. EEI uses a change oi'0 MW as the break p>>int.

F>>r larger po>>er reactors. 30 MW is ti~>> smail a change u> warrant cxplanaiio>>.

in accordance with the table appearing on the report form.

Ifcategory 4 must be used. suppiy brief comments.

LICENSEE EVENT REPORT =.

Reference the applicable reportable occurrence pertahing to the outage or power reduction.

Enter the ttrst four parts (event year. sequential report number, occ rrence code and report type) of the five part designation as described in Item 17 ot Instructions for Pr paration 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 turther 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 corr lation should be noted as not appiicab!e (NlA).

SYSTFM CODE.

The system in which the outaae or power reduction originated should be noted by the two digit code oi Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

Systems that do not ftt 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 comoonent.

C. If a chain of failures occurs, the first component to mai ~

function should be listed. The sequence of events. inciud-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 snould be de-signated XXXXXX. The code ZZZZZZ should be used ior events where a

component designation is not applicable.

CAUSE R CORRECTIVE ACTION TO PREVENT RECUR-,

RFRCE.

Use the column in a narrative fashion to ampiify or explain the circumstanc s of the shutdown or power reduction.

The column should include the specitic cause for each shut-down or significant power reduction and the immediate and

'contemplated Iong term corrective action taken. ifappropri-ate.

This column should also be used for a description of the major safety-related corrective maintenance performed durina the outage or power reduction inciuding an identification ot the critical path activity and a report of any single release of radioactivity>>r sinale radiation exposure specitically associ.

ated with the outage which accounts for more than 10 percent oi the allowable annual values.

For long textual reports cominue narrative on separate naper and ret'erence tlie shutdown or power reduction for this narrative.

UNITSIIUTI)01VNS ANI) POlVEf( REI)VCTIONS REI'ORThlONfll November, 1978 DOCKET NO.

50-316 Alga 2 l)ATE 12-14-78 COhlPLETED IN B.A. Svensson t PAGE 2 OF 2-N)).

l)atc El CLI-C

~-

L O

OK a-r)

IA J

)r, I) ~

)

Q O

W OQC e<)=

~ )I>

Llccnscc I>vent Rcpolt 4 V

p IJ Q p O

p(J

(.ause 8c Collective Actilnl I)>

Prcvcnl Recur fcl'Icc 42 43 781126 F

781130 F

11.2 0

N/A N/A HH ZZ TURBIN ZZZZZZ Turbine/Reactor trip due to trip of East Hain Feed Pump Turbine.

Unit returned to service 781127 and reactor power at 100Ã 781129.

Reactor power reduced to 55K due to problems created by induced currents in piping below main generator.

Re-actor power returned to 90% the same day.

I I': I'f)ICCJ S: SchcJ<<lcJ I))177)

Reason:

A-Efluipotcnt Failure (Explain)

Il-hlaiotcoance or Test

( Rcfoclloi',

D-RCI,ulatoly Restriction I:-Opcfator Ilanltoti4 License I:xaolioatioo F-AJotlolstlllllvc

(> Opcfatlooal LI'rl>r(Explahll I I.Other (Explai>> I 3 'lethoJ:

I hlaoual 2 hlaoual Scraol.

3.Autoolatic Scraln.

0-Other (Explain)

Exhibit G - Instnlcti)>os for Preparatio>> ol l)ata Lotry Sheets for l.iccoscc Event Rcp <<<<.I:i~i Flic INURI:(;-

Ol 6 I )

'I'exhibit I

~ Salnc Soulcc

UNITSHUTDOWNS AND POWER REDU

> S INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source oiexplan-ation or signiticant dips in average power levels.

Each signi-ficant reduction in powe.

I vel (gr ater than

>OPc reduction in averaae daily power level ior the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even thouah the unit may not have been shut down compietelyl.

For such reductions in power level, the duration should be listed as zero, the method of reduction should be iisted 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 signiiicant power reduction begins in one report period and ends in another.

an entry should be made for both report peiiods to be sure Jl shutdowns or significant power reductions are reported.

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

DATE.

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

Report as year. month. and day.

Auaust I '. 1977 would be reported as 770814.

When a shutdown or significant power reducrion begins in one report period and ends in another, an entry should be made for both report periods to be sure ail shutdowns or signiricant power reducuons are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche-duled," respeciively, ior each shutdown or siyuficant power reduction.

~ Forced shutdowns include those required to be initiated by no later than the weekend following discovery oi 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 acuon was taken.

DURATION.

Selfwxplanatory.

When a shutdown extends beyond the end oi a report period. count only the time to the end oi 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 facilitate summation.

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

REASON.

Categt>rize by letter designation in accordance with the iabie appearing vn the report torm. Ifcategory H must he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Caieaorize by number designation IN>oie that this difters i'rom the Edison Electric Institute IEEI) definitions of -Forced Partial Outage" and

-Sche-duled Partial Outage."

F>>r these terins. EEl uses a change ot'.0

~IW as the break p<>int.

F>>r larger p>>v er reactors.

SO MW is I>>>> small a change t>> warram explanati>ni.

in accordance with the table appearing on the report !orm.

Ifcategory 4 must be used. supply brief comments.

LICENSEE EVENT REPORT =.

Reference the appBcable reportable occurrence pertaining to the outage or powe.

reduction.

Enter the frst iour parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in ltein 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

This information may not be immediately evident for aII such shutdowns. of course, since further investigation inay be required to asc rtain 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 correiation shouid 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 oi Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

Systems that do not fit any exiting 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 coinponent from Exhibit I

~ Instrucuons for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416}).

using the following critieria:

A. Ifa component iailed, 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 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 snould be de.

signated XXXXXX. The code ZZZZZZ should be used ior events where a

component designation is not appiicable.

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 contemolated long term corrective action taken. ifappropri-ate.

This column should also be used for a description of the major safety-related corrective maintenance pertormed during the ouiage or power reduction including an identification of the critical path ac:ivity and a report of any single release oi radioactivity ur single radiation exposure specittnily associ

~

ated with the outage which accounts ior more than 10 pere nt oi the allowable annual values.

For long textual reports continue narrative on separate paper anu reference tlie shutdown or power reduction ior th>>

llaffative.

t Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

50-316 D.

C.

Cook Unit ¹2 R.

S. Keith (616) 465-5901 December 13, 1978 OPERATING EXPERIENCE --

NOVEMBER 1978 Hi hli hts The Unit was removed from service at 2125 hours0.0246 days 0.59 hours 0.00351 weeks 8.085625e-4 months November 9, 1978 for a planned outage for repairs to the Moisture Seperator Reheaters.

The outage was completed and the Unit paralleled with the system at 2235 hours0.0259 days 0.621 hours 0.0037 weeks 8.504175e-4 months November 25, 1978.

~Suvmav ll/01/78 The Unit entered this reporting period at 90K power and 870 megawatts electrical.

At 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months power was reduced to 80K as a conser-vation effort to keep the reheaters operating until the scheduled outage for repairs.

Power was reduced to 75K at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months to remove the "B" string of high pressure heaters from service for repairs to 5-B feedwater heater.

ll/02/78 Power was reduced to 60K to remove the West Main Feed Pump from service to repair a leak on the warming line.

Radiation Monitors R-31 and R-32 were out of service for one hour for preventive maintenance.

ll/03/78 The West Main Feed Pump was returned to service and the Unit was returned to 80K power starting at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months .

The "B" string of high pressure heaters was returned to service at 2155 hours0.0249 days 0.599 hours 0.00356 weeks 8.199775e-4 months .

ll/04/78 The Unit was. reduced to 754 power to remove the "A" string of low pressure feedwater heaters from service because of an indicated tube leak.

11/05/78 -- The Unit was. reduced to 50/ power and the "A" string of high pressure heaters was removed from service due to an indicated tube leak.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82 R.

S. Keith (616) 465-5901 December 13, 1978 (2) ll/06/78 The "A" string of low pressure heaters was returned to (cont) service at 1940 hours0.0225 days 0.539 hours 0.00321 weeks 7.3817e-4 months .

The Unit was returned to 80/

power starting at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months .

The Turbine Driven Auxiliary Feed Pump was inoperable from 0830 to 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months because the turbine would not reset.

The trouble was traced to a shorted diode in the electrical overspeed trip circuit.

ll/07/78 The "A" string of high pre'ssure heaters was returned to service at 1810 hours0.0209 days 0.503 hours 0.00299 weeks 6.88705e-4 months .

The Unit was loaded to 85K power.

11/09/78 At 1917 hours0.0222 days 0.533 hours 0.00317 weeks 7.294185e-4 months started increasing toward 100/ power in preparation for a Generator trip from 1005.

At 2020 hours0.0234 days 0.561 hours 0.00334 weeks 7.6861e-4 months it was found that the belts on both bus duct cooling fans were broken.

At 2051 hour0.0237 days 0.57 hours 0.00339 weeks 7.804055e-4 months 's the Unit was started down from 92K.

The Unit was tripped off the line at 2125 hours0.0246 days 0.59 hours 0.00351 weeks 8.085625e-4 months .

11/10/78 The cooldown to Mode 5 was started at 1305 hours0.0151 days 0.363 hours 0.00216 weeks 4.965525e-4 months .

The Unit entered Mode 4 at 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months .

ll/ll/78The Unit entered Mode 5 at 0056 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months .

11/13/78 11/21/7&--

At about 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months we experienced a hydrogen fire under the 5'2 Generator.

Water was used'o keep the area cool while the Generator was degassed and then refilled with C02.

The fire was out at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months .

Due to the quick actions of many people there was only minor damage as a result of the fire.

While raising the Reactor Coolant System pressure to 400 lbs.

and with the temperature at 180'F, we experienced leakage from the containment spray header into the upper volume of the containment.

The leakage was caused by RH-104-W not being completely closed.

ll/23/78 The Unit entered Mode 4 at 0002 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and Mode 3 at 1240 hours0.0144 days 0.344 hours 0.00205 weeks 4.7182e-4 months .

ll/24/78 At 0745 the main steam lines had been pressurized and the steam generator stop valves were opened.

At 0820 hours0.00949 days 0.228 hours 0.00136 weeks 3.1201e-4 months the Steam Generator stop valves were closed and the steam lines repressurized to repair 3

steam leaks.

At 0838 started pulling the shutdown banks.

At 1035 the shutdown banks were inserted because every time the bank selector switch was repositioned, the step counters counted a step and the rods did not move.

Docket i o.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R.

S. Keith (616) 465-5901 December 13, 1978 (3)

The rod control system was repaired and the shutdown rods were pulled.

The approach to criticality took from 1656 to 2106 hours0.0244 days 0.585 hours 0.00348 weeks 8.01333e-4 months because the control rods were stopped at many positions to permit measuring rod position indication voltages.

At 2145 the main Turbine was rolled with a vacuum of 25.5 inches.

At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months the Unit entered Mode l.

ll/25/78 - 0031 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months Reactor tripped due to low-low level in ¹3 Steam Gener-ator.

0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months Pulled the shutdown banks.

0148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months Reactor was critical.

0458 hours0.0053 days 0.127 hours 7.572751e-4 weeks 1.74269e-4 months 0558 hours Started the West Main Feed Pump.

Main Turbine was rolled with a vacuum of 25.5 inches.

Vacuum decreased to 24 inches while bringing the Turbine up to speed.

0607 hours0.00703 days 0.169 hours 0.001 weeks 2.309635e-4 months The Main Turbine tripped on high level in ¹4 Steam Gen-erator.

0835 hours0.00966 days 0.232 hours 0.00138 weeks 3.177175e-4 months 1343 hours Unit reentered Hode 1.

Tested the Main Turbine overspeed trips.

The 112%

overspeed trip did not trip at the required value and the Main Turbine was shut down.

1817 hours0.021 days 0.505 hours 0.003 weeks 6.913685e-4 months Roll.ed the Hain Turbine with 25 inches of vacuum.

1941 hours0.0225 days 0.539 hours 0.00321 weeks 7.385505e-4 months Hain Turbine overspeed trips were tested satisfactorily.

2235 hours0.0259 days 0.621 hours 0.0037 weeks 8.504175e-4 months The Unit was paralleled with the system.

ll/26/78 - 1745 hours0.0202 days 0.485 hours 0.00289 weeks 6.639725e-4 months The Reactor was at 98Ã power and about 1115 megawatts electrical.

1804 hours0.0209 days 0.501 hours 0.00298 weeks 6.86422e-4 months Started decreasing power to 75Ã because of a suspected leak in 5-A feedwater heater.

1913 hours0.0221 days 0.531 hours 0.00316 weeks 7.278965e-4 months Reactor was at 75K power and 770 megawatts electrical.

1957 hours0.0227 days 0.544 hours 0.00324 weeks 7.446385e-4 months The East Main Feed Pump tripped off the line.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 02 R.

S. Keith (616) 465-5901 December 13, 1978 (4) 2002 hours0.0232 days 0.556 hours 0.00331 weeks 7.61761e-4 months 2130 hours 2159 hours0.025 days 0.6 hours 0.00357 weeks 8.214995e-4 months 11/27/78 - 0611 hours0.00707 days 0.17 hours 0.00101 weeks 2.324855e-4 months 0712 hour s 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months 2200 hours The Unit tripped on low-low level in 84 Steam Generator.

The Reactor was critical.

The Main Turbine could not be rolled by steam because differential expansion was too high.

Rolled the Main Turbine with steam when it was found that the differential expansion alarm was incorrectly adjusted.

The Unit was in parallel with the system.

Star ted increasing loid from 50K power.

The Unit was at 83K'ower with the ".A" string of high pressure heaters still out of service.

At this power level, with the high pressure heater bypass fu'Ily open, it was calculated that the flow to the "B" string of high pressure heaters was 120K of normal.

ll/28/78 - 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months The Unit was loaded to 90K power.

11/29/78 - 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months The "A" string of high pressure heaters was returned to service.

1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ll/30/78 - 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months 1345 hours 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months 1710 thru 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months The Unit was at 100Ã power.

Radiation Monitors R-25 and R-26 were placed out of service at 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months because of a failed pump.

Power reduction to 90K was started to remove the "A" string of high pressure heaters from service.

Load reduction was accelerated when a pipe hanger from the Hydrogen line to the Generator was found red hot.

The Unit was settled out at 55K.

A power increase from 55/ to 905 was made.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 316 D.

C.

CfDK - UNIT NO.

2 12-14-78 B. A. Svensson 6 6 65-0 MAJOR SAFETY-RELATED MAINTENANCE NOVEMBER, 1978 M-1 M-5 No.

3 front bank cylinder of 2CD emergency diesel engine temperature indicated high relative to other cylinders.

"Pull card" readings were taken and the fuel rack on b3FB adjusted to balance temperatures.

Replaced pivot pin bushing and bonnet gasket on non-essential service water containment isolation check valve.

Bluing check of seat satis-factory.

No.

2 steam generator stop valve, MRV-220, had hydraulic line leakage.

Replaced "0" rings and reassembled.

Operational check was satisfactory.

CTS-120E and CTS-120W, containment spray check valves, indicated leakage during testing.

Valve internals cleaned and valves retested.

Hydraulic snubber, 2-GCS-S637, fluid reservoir was leaking.

Replaced cracked reservoir.

M-6 NLP-153, pressurizer level transmitter equalizing valve was leaking.

A new bonnet was installed.

M-8 M-10 M-ll M-12 RC-122 and RC-123, pressurizer spray control valve bypass valves had stem leakage.

Line was freeze plugged and the valve bonnet diaphragms were replaced.

CCW-244-72, CCW cooling to east main steam line penetration was not functioning.

The seat and plug were replaced and valve retested satis-factorily.

MS-136-4 and MS-136-1, steam generator stop valve body drains, bonnets were steam cut.

Valves were replaced.

MS-136-2 and MS-136-3, 82 and 83 steam generator stop valve boyd drains were steam cut.

The valves were replaced.

Main steam sample connection root valve for 81 steam generator was leaking.

Replaced valve.

Main steam sample connection root valve for 84 steam gnerator was leaking.

Replaced valve.

DOCKET NO.

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

COOK - UNIT NO.

2 12-14-78

~B..

Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE NOVEMBER, 1978 Containment spray heater check valves, CTS-127E and CTS-127W would not pass flow.

Found valves installed backward.

Removed valves and rein-stalled properly.

Containment spray eductor check valve, CTS-120E was leaking.

The disc was cleaned and repositioned.

Retest was satisfactory.

The turbine driven auxiliary feedpump would not reset.

The input zener diode of the electronic tachometer required replaceme~t.

Calibration of the tachometer was performed and operability verified.

Flux mapping system detector A would not withdraw.

The reversing relay required replacement.

Rod position indication for control bank D rod H-8, indicated 13 steps from demand.

The secondary coil voltage was measured at 16.49 VAC which indicated the correct rod position of 207 steps as indicated on the step counter.

The signal conditioning module was respanned to the correct calibration.

The correct indication returned to the panel meter.

The step counter for shutdown bank C stopped counting at 46 steps.

The capacitor across contacts 5 and 6 of K19 relay in the logic cabinet required replacement.

Correct operation of the step counter was veri-fied.

Nuclear instrumentation system channel N31 source range indication was erratic.

The connectors of the high voltage and signal cable were cleaned and the channel returned to service.

The rod position indication system for control bank "D" rod H-8, rod bottom light extinguished while the panel meter indicated 25 steps.

The zero potentiometer of the signal conditioning module was adjusted.

The panel meter's indication returned to zero.

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ML17317A813

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