REC:NRC

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDDISTRIBUTION FOR INCOMING MATERIAL

ORG: SHALLER D VIN 5 Ml PWR

DOCTYPE: OTHER NOTARIZED: NOSUBJECT:MONTHLY OPERATING REPT FOR JANUARY 1978 — UNITS 1 5 2.

15/ 16

DOCDATE: 02/i0/78DATE RCVD: 02/14/78

COPIES RECEIVEDLTR 1 ENCL 1

PLANT NAME: COOK — UNIT 1

COOK — UNIT 2REVIEWER INITIAL: XJMDISTRIBUTER INITIAL:

+++++++++++++++4+ DISTRIBUTION OF THIS MATERlAL IS AS FOLLOWS

MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.(DISTRIBUTION CODE A003)

FOR ACTION:

INTERNAL:

EXTERNAL:

BRANCH CHIEF DAVIS++W/2 ENCL

EG FILE~~W/EWPG~

LPDR'SST. JOSEPH) MI4+W/ENCL

. TIC++W/ENCLNS IC4 +W/ENCLBNL(NATLAB>++W/ENCLACRS CAT B4+W/0 ENCL

NRC PDR4+W/ENCL

DISTRIBUTION: LTR 10 ENCL 10SIZE: 1P+9P+6P

4'%'3f"3I'')HE-3l"3l-3f"3f'4'%'3l'%%'3l'4'4'%'3l'%"54'%'3l-3l"3l'4"3l'4'4"3f'ONTROL

NBR: 780460261p) p

THE END

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INDIANA& NII:HIGANPDkVER CDNPANYDONALD C. COOK NUCLEAR PLANTP.O. Box 468, Bridgman, Michigan 49106

il

February 10, 1978

IIQI,pgg(((I FILEggitjy

~(

»p.uLi(Lg -'FE824)9@a

Director, Office of Management Informationand Program Control

U. S. Nuclear Regulatory CommissionWashington, D.C. 20555

Gentlemen:

Pursuant to the requirements of Donald C. Cook Nuclear Plant Units 1

and 2 Technical Specification 6.9.1.6, the attached Monthly OperatingReports for the month of January, 1978 are submitted.

Sincerely,

D. V. ShallerPlant Manager

DVS:ab

Attachments

cc: R. W. JurgensenNRC Region IIIK. R. BakerR. C. CallenR. WalshS. J. MierzwaJ. E. DolanR. J. VollenG. E. LienK. W. BrownJ. M. HenniganP. W. SteketeeA. F. KozlowskiJ ~ F. StietzelPNSRC File

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APPENDIX BAVERAGE DAILYUNIT POWER LEVEL

DOCKET NO.

UNIT2-1-78

COMPLETED gY H. T. GillettTELEPHONE 61 6-465-5901

MONTH January 1978

DAY AVERAGE DAILYPOWER LEVEL(MWe-Net)

1043

1045

1045

DAY AVERAGE DAILYPOWER LEVEL(ice-iNet)

59917

18

463

10

12

13

14

15

16.

914

806

557

412

10

836

1039

1040

1041

1025

49

70

897

20

21

23

24

25

26

28

29

31

103.'039

1046

1044

1044

1042

1045

1046

1044

1046

1043

1043

INSTRUCTIONSOn this form, list the average daily unit power level in M)Ve.iiet for each day in the reporting month. Compute to thenearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is

used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the

100% line (or the restricted power level line). in such cases, the average daily unit power output sheet should be

footnoted to explain the apparent anomaly.1.16-8

OPERATING DATAREPORT

DOCKET F40.

DATECOIIPLETED I)Y W. T. Gillett

TELEPHONE

OPERATING STATUS

I Umt Name Donald C. Cook 1

3. Licensed Thermal Power (MWt):4. Nameplate Rating (Gross MWe):5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

10801044

Notes

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 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 Cumuhtive

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line15. Unit Reserve Shutdown Hours16. Gross Thermal Ener y Generated (MWH)17. Gross Electricai Energy Generated (MWH)18. ii'et Electrical Energy Generated (MWH)19. Unit Service Factor20. Unit Availability Factor21. Un!t Capacity Factor (Using i~fDC Net)22. Unit Capacity Factor (Using DER Net)23. Unit Forced Outage Rate24. Shutdowns Scheduled Over Next 6 Months (

4-1-.78 Refueling Outage

744645.3

0637.9

1,923,060633,500610, 160

85. 7

85. 778.5

645;3

637.90

1,923,060633,500610,160

85. 7

85. 7

7 ~

27 04821,268.0

463.020.607.7v-

'21.,0

53,479, 25317,3, 0

16,660,37480. 4

80.468.8

77.8 63.414.3 7.2

77.814.3

Type. Date. and Duration of Each):6 weeks

25. IfShut Down At End Of Report Period. Estimated Date of Startup:26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved

INITIALCRITICALITYINITIALELECTRICITYCOMMERCIAL OPERATION

(i)/77 )

1 of 2

UNITSIIUTDO)VNS AND PO)VER REDUCTIONS

REPORThIONTII JANUARY, 1978

DOCKET NO.UNITNAME

DATECOMPLETED IIY

TELEP)IONE

2JLIB—'.

A. Svensson

N)). l)atc

P)

CA

LlccusccEvent

Rcport rr

)))~o ~Q)= ~

Cr

Cause &, CorrcctivcAction to

Prcvcnt Rccurrcnce

117

118

119

120

780104

780106

780107

780113

0 H

,0

31.9 A

39.5 A

N/A

N/A

N/A

N/A

l)JC VALVEX

zz zzzzzz

HA PUMPXX

HA PUMPXX

Reduced reactor power to 50K due tohigh steam generator conductivitycaused by leak through from makeupplant. Increased power to 1005780105

'educed reactor power to 505 tosupply steam to Unit No. 2 mainturbine initial roll.Increased power to 100% 780107.

Unit removed from service due toproblems with turbine EHC oil. system.Unit returned to service 780108.At 1005 power 780109.

Unit removed from service due to-problems with turbine EHC oil system.Unit returned to service 780115.At lOOX power 780116.

F: ForcedS: Scheduled

Reason:A-Erluipmcnt Failure (Explain)I).hlaintcnance or TestC-RefuelingD ltegulatory RcstrlctlonE-Operator Training Ec License I'.xanlinationF-AdministrativeG Operational El n)r (I'.xplain)li Other (Explain)

3hlethod:I.hlanual2 htanual Scfaul.3-Automatic Scralu.4.Other (Explain)

4Exhibit G - InstructionsI'or Preparation of DataLntry Sheets lor LicenseeEvent Report-(LER) Fil (NUREG-OI6I)

Exlublt I ~ Saluc Source

UNITSHUTDOWNS AND POWER REDUCTIONS

INSTRUCTIONS

This report should describe all plant shutdowns during thereport period. In addition, it should be the source ofexplan-ation of significant dips in average po'wer levels. Each signi-ficant reduction in power level (greater than 2(Ffo reduction

~ in average daily power level for the preceding 24 hours)should be noted, even though the unit may not have beenshut down completely1. For such reductions in power level,the duration should be listed, as zero, the method of red'uctionshould be listed as 4 (Other), and the Cause and CorrectiveAction to Prevent Recurrence column should explain. TheCause and Corrective Action to Prevent Recurrence columnshould be used to provide any needed explanation to fullydescribe 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 powerfor that calendar year. When a shutdown or significant powerreduction begins in one report period and ends in another.an entry should be made for both report periods to be sureall 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 startof each shutdown or significant power reduction. Reportas year, month, and day. August i4. 1977 would be reportedas 770814. When a shutdown or significant power reductionbegins in one report period and ends in another, an entry shouldbe made for both report periods to be sure all shutdownsor significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant powerreduction. Forced shutdowns include those required to beinitiated by no later than the weekend following discoveryof an off.normal condition. It is recognized that some judg-ment is required in categorizing shutdowns in this way. Ingeneral, a forced shutdown is one that would not have beencompleted in the absence of the condition for which correctiveaction was taken.

DURATION. Self<xplanatoty. When a shutdown extendsbeyond the end of a report period, count only the time to theend ot the report period and pick up the ensuing down timein the following report pericles. Report duratibn of outagesrounded 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 reportingperiod.

REASON. Categorize by letter designation in accordancewith the table appearing on the report t'orm. Ifcategory Hmust be used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR ORREDUCliVG POWER. Categorize by number designation

INole that this differs l'rom the Edison Electric InstitutetEEI) definitions of -Forced Partial Outage" and -Sche.duied Partial Outage." For these tern». I.EI uses a change

ot'0

MW as the break point. For larger power reactors. ~0 MWls tc>o slllJll J change tl) WJfl'Jnl explJnallllll.

in accordance with the table appearing on the report form.Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT —.. Reference the applicablereportable occurrence pertaining to the outage or powerreduction. Enter the first four parts (event year. sequentialreport number, occurrence code and report type) of the fivepart designation as described in Item 17 of Instructions forPreparation of Data Entry Sheets for Licensee Event Report(LER) File (NUREG4161). This information may not beimmediately evident for all such shutdowns, of course, sincefurther investigation may be required to ascertain whether ornot'a reportable occurrence was involved.) If the outage orpower reduction will not result in a reportable occurrence.the positive indication of this lack of correlation should benoted as not applicable (N/A).

SYSTEM CODE. The system in which the outage or powerreduction originated should be noted by the two digit code ofExhibit G - instructions for Preparation of Data Entry Sheetsfor 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 wherea system is not applicable.

COMPONENT CODE. Select the most appropriate componentI'lom Exhibit I ~ Instructions for Preparation of Data EntrySheets 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 mal-function should be listed. The sequence of events, includ-ing the other components which fail, should be describedunder 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 forevents where a component designation is not applicable.

CAUSE Sc CORRECTIVE ACTION TO PREVENT RECUR-RENCE. Use the column in a narrative fashion to amplify orexphin 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 andcontemplated long term corrective action taken. ifappropri-ate. This column should also be used for a description of themajor safety rehted corrective maintenance performed duringthe outage or power reduction including an identification ofthe critical path activity and a report of any single release otradioactivity or single radiation exposure specitlcally asso«i-ated with the outage which accounts for more than 10 percentof the allowable annual values.

for long textual reports continue narrative on separate paperand ret'erence the shutdown or power reduction t'or tiu>n JrfJt lve.

(9/77

20f2

UNITSIIUTDO)UNS AND PO)UER REDUCTIONS

REPORT MON f)» JAf'(VARY, 1978

DOCKET NO.

&L28-COh(PLETED DY

TELEPllONE 61 6 465-5

l)alclAL

r)L

0A J

Q

LiccosccEvent

Rcport 4

Co~() QQ C)

)O

Cause &, CorrcclivcAt:tion lo

Prcvcol Rccurrcnce

121 780117 F 34.7 H H/A L1C VALVEX Unit removed from service due toleak through from makeup 'plantcausing high conductivity in allsteam generators. Returned toservice 780119. At 1005 power780120.

I

I': ForcedS: Schedule)I

Reason:A-Ecluipn)ent Failure (Explaio)D.hlaittlenance or TestC.RefuelingD-Regulatory RestrictionE-Opecaloc Training & License IixamioationF-Administ ca liveG Opccattol)al L)rur (I'.xplatn)I I Other (Explairt)

hlethod:I-Manual2.h(aoual Sera)n.3-Ante)marie Scrato.4-Other (Explato)

Exhibit G - InstructionsI'or Preparation ol DataEntry Sheets I'or Lice))see .

Event Report (LER) Fil (NUREG-OI 6 I )

'Exhibit I - Sao)c Source

0 ~UNITSHUTDOWNS AND POWER REDUCTIONS

INSTRUCTIONS

This report should describe all plant shutdowns during thereport period. In addition, it should be the source ofexplan-ation of significant dips in average po'wer levels. Each signi ~

ficant reduction in power level (greater than 2(Y/o reductionin average daily power level for the preceding 24 hours)should be noted, even though the unit may not have beenshut down completelyl. For such reductions in power level,the duration should be listed. as zero, the method of reductionshould be listed as 4 (Other), and the Cause and CorrectiveAction to Prevent Recurrence column should explain. TheCause and Corrective Action to Prevent Recurrence columnshould be used to provide any needed explanation to fullydescribe 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 powerfor that calendar year. When a shutdown or significant powerreduction begins in one report period and ends in another.an entry should be made for both report periods to be sureall 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 startof each shutdown or significant power reduction. Reportas year, month, and day. August i4. 1977 would be reportedas 770814. When a shutdown or significant power reductionbegins in one report period and ends in another, an entry shouldbe, made for both report periods to be sure all shutdownsor significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either "Forced" or "Sche.duled," respectively, for each shutdown or significant powerreduction. Forced shutdowns include those required to beinitiated by no later than the weekend following discoveryof 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 beencompleted in the absence of the condition for which correctiveaction was taken.

DURATION. Self<xplanatory. When a shutdown extendsbeyond the end of a report period, count only the time to theend of the report period and pick up the ensuing down timein the following report periods. Report duration of outagesrounded 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 reportingperiod.

REASON. Categorize by letter designation in accordancewith the table appearing on the report form. Ifcategory Hmust he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR ORREDUCING POWER. Categorize by number designation

INote that this differs t'rom the Edison Electric InstituteIEEI) definitions ot -Forced Partial Outage" and -Sche-duled Partial Outage." For these taint~. F.EI uses a change

oi'0

41W as the break point. For larger power reactors. 30 MWis ti|o small a cliange tii warrant explanation.

in accordance with the table appearing on the report form.Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT -... Reference the applicablereportable occurrence pertaining to the outage or powerreduction. Enter the first four parts (event year. sequentialreport number, occurrence code and report type) of the fivepart designation as described in Item 17 of Instructions forPreparation of Data Entry Sheets for Licensee Event Report(LER) File (NUREG4161). This information may not beimmediately evident for all such shutdowns, of course, sincefurther investigation may be required to ascertain whether ornot'a reportable occurrence was involved.) If the outage orpower reduction will not result in a reportable occurrence.the positive indication of this lack of correlation should benoted as not applicable (N/A).

SYSTEM CODE. The system in which the outage or powerreduction originated should be noted by the two digit code ofExhibit G - Instructions for Preparation of Data Entry Sheetsfor 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 wherea system is not applicable.

COMPONENT CODE. Select the most appropriate componentfrom Exhibit I - Instructions for Preparation of Data EntrySheets 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 ascomponent.

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 describedunder 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 forevents where a component designation is not applicable.

CAUSE 8c CORRECTIVE ACTION TO PREVENT RECUR-RENCE. Use the column in a narrative fashion to amplify orexplain 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 andcontemplated Iong term corrective action taken. ifappropri-ate. This column should also be used for a description of themajor safety-related corrective maintenance performed duringthe outage or power reduction inciuding an identification ofthe critical path activity and a report of any single release ofradioactivity ur single radiation exposure specitically associ ~

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

For long textual reports continue narrative on separate paperand reference ilie shutdown or power reduction for thiillarratlve.

(9/77

Docket No.Unit Name

DateCompleted by

Telephone

50~315D C. C ok - U it . 1

2- -78R

OPERATING EXPERIENCE - JANUARY, 1978

HIGHLIGHTS

Unit 1 started the New Year operating at 100% power.

Steam from Unit 1 was used to conduct the initial rolling of Unit2 Turbine

Generator.'wo

separate instances of acid entering the Condensate System duringresin regeneration of the Demineralized Water Make-Up Plant forced a reductionin power while working to reduce Steam Generator conductivity.

SUMMARY

1/4

At the beginning of the month the unit was operating at lOOXpower.

Unit load~was reduced to 45K due to high conductivity inSteam Generators which was caused by acid getting into theCondensate System while regenerating resin i.n the Make-UpPlant.

1/6

1/7

1/8

1/13

1/15

1/17

1/1.8

1/19

1/20

1/31

The unit -load was reduced to 504 and steam from Unit 1 usedto perform the initial rolling of Unit 2 Turbine Generator.

The unit was shutdown to make repairs to the Turbine Genera-tor Electro-Hydraulic Control (EHC) System.

Reactor was critical at 2008 hours and the Generator parralleledwith the system at 2222 hours.

The unit was shutdown to make repairs to the EHC System.

Reactor was critical at 1546 hours and the Generator parralleledto the system at 1852 hours.

The unit was shutdown from 1004 due to high conductivity inSteam Generators which was caused by acid getting into theCondensate System while regenerating resin in the Make-UpPlant

Reactor was critical at 2326 hours.

Generator parralleled with the system at 0136 hours.

The unit was at 100K power at 1100 hours.

The unit had been at 100/ power since 1/20/78.

DOCKET NO.UNIT NAME

DATECOMPLETED BY

TELEPHONE

50 - 315D. C. Cook - Unit No. 1

2-10-78B. A. Svensson

616 465-5901

MAJOR SAFETY-RELATED MAINTENANCE

JANUARY, 1978

M-1

M-2

M-3

C&I-1

HARV-51, alternate supply to pressurizer spray, had broken packing glandstuds and the packing had blown out. Installed new gland studs andrepacked valve.

DG-145C, CD'iesel jacket water heater outlet check valve was stuck open.Cleaned valve and relieved binding. Relapped valve seat.

During surveillance testing, ¹2 boric acid transfer pump discharge pressurewas 4 psig lower than the minimum. Replaced leaking mechanical shaft sealand had pump retested.

DG-117A, AB2 diesel starting air compressor strainer valve leaked by. Stemwas badly bent. Replaced valve.

Recorder MR-36, refueling water storage tank level recorder, indicated offscale on the high end. The level transmitter ILA-950, calibration wasfound to be out of specifications. The transmitter calibration was per-

'ormed and returned to service. The correct level of the RWST was 98/.

C&I-2 The CD emergency diesel fuel oil storage tank indicated a low and highalarm condition. The level of the tank was verified at 9.6 feet. Themercoid instruments, providing the alarm functions, setpoints are adjustedto a low value (psi), the reset of the instruments require a large changeof level. The instrument was manually reset and correct operation of thealarm was verified.

C&I-3

C&I-4

The C02 protection for the 4KV room switch gear cable vault would notreset. The alarm bell relay was found to be mechanically latched. Therelay required physically resetting. Hazard 7 was retested and clearedthe red light by opening the knife switch and reclosin'g the switch. Thereset push button then was depressed. The control system functionedproperly.

RRV-306, gas release trip valve failed to open as required by the controlcircuit. A loose connection at the fuse in the control circuit had removedcontrol power. The fuse clips were tightened and the fuse reinstalled.

,Correct valve operation was verified.

DOCKET NO.UNIT NAME

DATEPAGE

50 - 315D. C. Cook - Unit No. 1

2-10-78

MAJOR SAFETY-RELATED MAINTENANCE

JANUARY, 1978

CRI-5 Rod position indication for rod F-6 on shutdown bank D deviated 12 stepsfrom the associated bank. The signal condition module voltage was foundto be greater than required, The module calibration was performed andcorrect indication returned.

CSI-6

CSI-7

CSI-8

DCR-340, steam generator blowdown isolation valve, limit switches wereout of adjustment which prevented DCR-340 from remaining open, Thecoupling and limit switch actuator were adjusted for correct operation.The valves operation was verified and timed.

Nuclear instrumentation intermediate channel N-35, displayed an "indi-cation while the reactor. has been shutdown. The discrimination voltageon the drawer assembly required adjustment.

Rod position indication for control K6, remained at 129 steps. Thevoltage from the RPI coils was verified as correct. The signal con-ditioning module required recalibration. Following calibration, correctcontrol room indication for K6 was verified.

CSI-9 RRV-285, waste disposal system automatic trip valve operated from RMS

channel R-18, failed to close completely. The problem was identified aspressure within the line between RRV-287 and WD-166. Following thecycling of RRV-287, operatio'n of RRV-285 was verified.

C&I-10 NLP-151, pressurizer level protection set I, indicated 6g higher thanthe remaining channels. Mater was pumped through the equalizing line tocompletely fill the condensing pot and associated instrument line. Theindication of NLP-151 returned to within specifications.

AVERAGE DAILYUNIT POWER LEV

~ ~ I7 ~

DOCKET NO.

D C Cook 2

DATE2-9-78

CO'qPI ETED gY W. T. Gillet-t

T~> EPHONE616-465-5901

ONTHJanuary 1978

DAY AVERAGE DAILYPOWER LEVEL(MWe-Net )

I0

DAY AVERAGE DAILYPOWER LEVEL(M

We-Net�

)

017

3

10

12

13

14

15'6

0

0

0

0

0

0

0

0

0

0

0

0

18

19

20

21

23

%5

26

27

28

'>9

30

31

0

0

0

0

0

0

0

0

0

0

0

0

0

0

INSTRUCTIONS

On this format. list th ave." ge daily unit povver level in ~I~Ve.Net for each day in the reportin8 >ni>nth. C»rnpute to

the nearest v'hole m gavvatt.

{t)r771

~ ~

OPERATING DATAREPORT

DOCKET NODATE 2-9-78

COMPLETED BY W. T. GillettTELEPHONE ~~01

OPERATING STATUS

Donald C. Cook 2

2. Reporting period: JanuarY 1978

3. Licensed Thermal Po~er (MWt):4. Nameplate Rating (Gross MWe):5. Design Electrical Rating (Net ibIWe):

1100

6. Maximum Dependable Capacity (Gross MWe):7. Maximum Dependable Capacity (Net MWe):

11181082

Notes

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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

10 Reasons For Restrictions IfAnv. Until commission has approved the WRB-1 correlationand the improved thermal design procedure WCAP-8762 and WCAP-8567.

This Month Yr.-to-Date Cumuhtive

11. Hours In Reporting Period12. Number Of Hours Reactor Was Critical13. Reactor Reserve Shutdown Hours14. Hours Generator On-Line15. Unit Reserve Shutdown Hours16. Gross Thermal Energy Generated (MWH)l 7. Gross Electrical Energy Generated (i%IWH)18. Net Electrical Energy Generated (iiIWH)19. Unit Service Factor20. Unit Availability Factor21. Un!t Capacity Factor (Using MDC Net)22. Unit Capacity Factor (Using DER Net)23. Unit Forced Outage Rate24. Shutdowns Scheduled Over Next 6 Months

744

00

0

00000

(Type. Date. and Duration of Each):

25. IfShut Down At End Of Report Period. Estimated Date of Startup:26. Units In Test Status (Prior to Commercial Operation):

INITIALCRITICALITYINITIALELECTRICITYCOi~DIERCIALOPERATION

Forecast

3/1/783/13/786/3/78

Achieved

UNITSI IUTDO'IVNS AND POPOVER REDUCTIONS

e

DOCKET NO.D.C.COOK - UNIT NO, 2

REI'ORTh(ON.fll JANUARY, 1978

Nc). l)ale

r)

)J

=)) -"

Q~ C/l

LiccosccEvent

Report 4

CcCl El

'e)~A

I/)'r

CJ~o ~I) o

O

Cause & CoffcclivcAclh)o to

Pfcvclll Rccllffcoce

0 771223 S 744 N/A zzzzzz Facility Operating LicenseNo. DPR-74 was issued onDec. 23, 1977. Initial fuelloading commenced 'on Dec. 26, 1977and was completed on Jan. 2, 1978.Preparations for initial startupa'e in progress.

I: FoleellS: Schell«lcll

(')/77)

Reason:A.flluipolenl Failure (Explain)lib(aiotcnaoce oi TestC.Rer«elhi(;D.Ret,ulat ofy Rest riel ionE-Operator Traioiol; & Lice»se L'xaoliopliooI'-AlhninistIa I iveG Operation))I LIfor (I'.xplaio II l.other {Expl:unl

3hlcthod:I.Manual')-h(annal Scralo.3-Autoolalic Scraol.'I.Other {Explanl)

4Exhibit C - Instructionsfor Preparation ol'DataEntry Sheets lor l.ieensecEvent Report (I.I!R) I'ile (NURIIG-Ol 6l )

'Exhibit I =Saute Source

UNITSHUTDOWNS AND POWER REDU i i S

INSTRUCTIONS 4 ~ ~

This report should describe all plant shutdowns during thereport period. In addition, it should be the source ofexplan-ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 2(Yfc reduction::in average daily power level for the preceding 24 hours)should be noted, even though the unit may not have beenshut down completely 1. For such reductions in power level,the duration should be listed as zero, the method of reductionshould be listed as 4 (Other), and the Cause and CorrectiveAction to Prevent Recurrence column should explain. TheCause and Corrective Action to Prevent Recurrence columnshould be used to provide any needed explanation to fullydescribe the circumstances of the outage or power reduction.

NUiMBER. This column should indicate the sequential num.ber assigned to each shutdov n or significant reduction in powerfor that calendar year. When a shutdown or significant powerreduction begins in one report period and ends in another,an entry should be made for both report periods'to be sureall shutdowns or significant 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 of the startof each shutdown or signittcant power reduction. Reportas year. month. and day. Auaust i4. 1977 would be reportedas 770814. iVhen a shutdown or significant power reductionbegins in one report period and ends in another, an entry shouldbe made for both report periods to be sure all shutdownsor significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either "Forced" or "Scne-duled," respectively, ior each shutdown or significant powerreduction. Forced shutdowns include those required to beinitiated by no later than the weekend following discoveryof an oif.normal condition. It is recognized that some judg-ment is required in categorizing shutdowns in this way. Ingeneral. a forced shutdown is one that would not have beencompleted in the absence of the condition for which correctiveaction was taken.

DURATION. Seifwxplanatory. When a shutdown extendsbeyond the end of a report period, count only the time to theend ot the report period and pick up the ensuing down timein the following report periods. Report duration of outagesrounded to the nearest tenth ofan hour to facilitate summation.The sum of the total outage hours plus the hours the aenera.tor was on line should equal the gross hours in the reportingperiod.

REASON. Categorize by letter designation in accordance;with the table appearing on the report form. Ifcategory Hmust be used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR ORREDUCING POWER. Caieaorize by number designation

INoie that this differs t'rom the Edison Electri InstitutetEEI) definitions ot'Forced Partial Outage" and -Sche.duled Partial Outage." Fiir these tern». I;El uses a change of:0!~IW as the break point. Fiir larger power reactors. ~0 51W

is iii i small a change to warrant explanation.

in accordance with the table appearing on the report formIfcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT ='. Reference the applicablereportable occurrence pertaining to the outage or powerreduction. Enter the first four parts (event year. sequentialreport number, occurrence code and report type) of the tivepart designation as described in Item 17 of Instructions forPreparation of Data Entry Sheets for License Event Report(LER) File (iiIUREG4161). This information may not beimmediately evident for all such shutdowns, of,course, sincefurther investigation may be required to ascertain whether ornot a reportable occurrence was involved.) If the outage orpower reduction will not result in a reportable occurrence.the positive indication of this lack of correlation should benoted as not appiicable (N/A)..

SYSTF&i CODE. The system in which the outage or powerreduction originated should be noted by the two digit code otExhibit G - Instructions for Preparation of Data Entry Sheetsfor 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 wherea system is not applicable.

lV'OiMPONENT

CODE. Select the most appropriate componentI'rom Exhibit I - Instructions for Preparation of Data EntrySheets 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:gist 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 describedunder 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 forevents where a component designation is not apolicable.

CAUSE &, CORRECTIVE ACTION TO PREVENT RECUR-RENCE. Use the column in a narrative fashion to ampiify orexplain the circumstances of the shutdown or power reduction.The column should include the specific cause for each shut ~

down or signirtcant power reduction and the immediate andcontemplated long term corrective action taken, if appropri-ate. This column should also be used for a description,ot themajor safety. related corrective maintenance performed'duringthe outage 'or power reduction including an identificarion o!the critical path ac;ivity and a report of any single release ofradioactivity i/r single radiation exposure specitically associ ~

ared with the outage which accounts for more than 10 percentof the allowable annual values.

For long textual reports continue narrative on separate paoeranu reference tlie shutdown or power reductiun foi thisliarrative.

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DOCKET NO.UNIT NAME

DATECOMPLETED BY

TELEPHONE

MAJOR SAFETY-RELATED MAINTENANCE

50 - 316D. C. Cook - Unit No. 22-10-78B. A. Svensson

616 465-5901

JANUARY, 1978

M-2

M-3

IFI-320, RHR heat exchanger outlet flow meter impulse line was leaking.Replaced pipe nipple.

Part length control rod drive conoseal seating surfaces were found tohave been slightly scored during construction, Repaired seating surfaces.

612'levation personnel air lock door interlock was broken. Replaced2 interlock cables, adjusted interlock and had door retested.

Equalize line around RH-128E was broken. Replaced 1/2" tubing forequalizing line.

M-5 , A small fuel oil leak developed on a line from the fuel injection pump tothe top of 0'8 cylinder on AB diesel. Replaced fuel injection line and hadit operationally tested.

M-6

M-7

M-9

M-10

M-11

M-12

f1-13

The shutdown cylinder diaphragm in AB diesel leaked. Replaced shutdowncylinder diaphragm and had ending tested.

The gear train on the 650'levation airlock door to containment broke.Replaced one broken gear and tested interlocks.

Emergency order to repair leaking fuel injection line on AB diesel.Replaced fuel injection line.

Pop tested fuel injectors on 1,3,5 front bank and 4 rear bank cylinders ofAB diesel. Also replaced leaking turbocharger discharge gasket and hadengine tested.

Replaced leaking injector supply line on CD diesel and retested.

A weld leak was discovered on an RHR vent line near RH-125E. Replaced aone inch pipe nipple.

A crack developed in the socket weld at the downstream side of IM0-222,the "W" containment spray pump recirc valve. Ground weld out and rewelded.Hydrostatic test was performed at 550 psig.

SV-102, the safety valve on RHR line to loops 2 and 3 was leaking.Replaced bellows assembly and reset safety,

DOCKET NO. 50 - 316UNIT NAME''""'""D. C-. Cook - Unit No. 2DATE 2-10-78PAGE 2

MAJOR SAFETY-RELATED MAINTENANCE

JANUARY, 1978

CD diesel crankcase relief cover on 85 front bank was leaking. Replacedgasket.

CD diesel rear bank jacket water head to outlet manifold gaskets leaked.Replaced gaskets.

An oil line on the oil cooler for k'3 RCP motor was leaking. Replaced theoil line and .fittings.

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