Text

Letter Monthly Operating Report for January 1978
	ML18219D352
Person / Time
Site:	Cook
Issue date:	02/10/1978
From:	Shaller D; American Electric Power, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML18219D352 (19)
	v • d • e

REC:

NRC REGULATORY INFORMATION DISTRIBUTION SYSTEM (RID DISTRIBUTION FOR INCOMING MATERIAL ORG:

SHALLER D V

IN 5 Ml PWR DOCTYPE:

OTHER NOTARIZED:

NO

SUBJECT:

MONTHLY OPERATING REPT FOR JANUARY 1978 UNITS 1 5 2.

15/

16 DOCDATE: 02/i0/78 DATE RCVD: 02/14/78 COPIES RECEIVED LTR 1

ENCL 1

PLANT NAME: COOK UNIT 1

COOK UNIT 2 REVIEWER INITIAL:

XJM DISTRIBUTER 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/E WPG~

LPDR'S ST.

JOSEPH)

MI4+W/ENCL

. TIC++W/ENCL NS IC4 +W/ENCL BNL(NATLAB>++W/ENCL ACRS CAT B4+W/0 ENCL NRC PDR4+W/ENCL DISTRIBUTION:

LTR 10 ENCL 10 SIZE:

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/IElecteio INDIANA& NII:HIGANPDkVER CDNPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 468, Bridgman, Michigan 49106 il February 10, 1978 IIQI,pgg(((I FILEggitjy

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>>p.uLi(Lg -'

FE824)9@a Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, 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 Operating Reports for the month of January, 1978 are submitted.

Sincerely, D.

V. Shaller Plant Manager DVS:ab Attachments cc:

R.

W. Jurgensen NRC Region III K.

R.

Baker R.

C. Callen R. Walsh S. J.

Mierzwa J.

E. Dolan R. J. Vollen G.

E. Lien K.

W.

Brown J.

M. Hennigan P.

W. Steketee A. F. Kozlowski J

~

F. Stietzel PNSRC File p5 happ Spq6p~6

APPENDIX B AVERAGEDAILYUNIT POWER LEVEL DOCKET NO.

UNIT 2-1-78 COMPLETED gY H. T. Gillett TELEPHONE 61 6-465-5901 MONTH January 1978 DAY AVERAGEDAILYPOWER LEVEL (MWe-Net) 1043 1045 1045 DAY AVERAGE DAILYPOWER LEVEL (ice-iNet) 599 17 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 INSTRUCTIONS On this form, list the average daily unit power level in M)Ve.iiet for each day in the reporting month. Compute to the nearest 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.

DATE COIIPLETED 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):

1080 1044 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 Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Ener y Generated (MWH)

17. Gross Electricai Energy Generated (MWH)

18. ii'et Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Un!t Capacity Factor (Using i~fDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (

4-1-.78 Refueling Outage 744 645.3 0

637.9 1,923,060 633,500 610, 160

85. 7

85. 7 78.5 645;3 637.9 0

1,923,060 633,500 610,160

85. 7

85. 7 7

~

27 048 21,268.0 463.0 20.607.7v-

'21.,0 53,479, 253 17,3, 0

16,660,374

80. 4 80.4 68.8 77.8 63.4 14.3 7.2 77.8 14.3 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 INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION (i)/77 )

1 of 2 UNITSIIUTDO)VNS AND PO)VER REDUCTIONS REPORThIONTII JANUARY, 1978 DOCKET NO.

UNITNAME DATE COMPLETED IIY TELEP)IONE 2JLIB A. Svensson N)).

l)atc P)

CA Llccuscc Event Rcport rr

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Cr Cause &, Corrcctivc Action 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 to high steam generator conductivity caused by leak through from makeup plant.

Increased power to 1005 780105

'educed reactor power to 505 to supply steam to Unit No.

2 main turbine initial roll.

Increased power to 100% 780107.

Unit removed from service due to problems 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: Forced S: Scheduled Reason:

A-Erluipmcnt Failure (Explain)

I).hlaintcnance or Test C-Refueling D ltegulatory Rcstrlctlon E-Operator Training Ec License I'.xanlination F-Administrative G Operational Eln)r (I'.xplain) li Other (Explain) 3 hlethod:

I.hlanual 2 htanual Scfaul.

3-Automatic Scralu.

4.Other (Explain) 4 Exhibit G - Instructions I'or Preparation of Data Lntry Sheets lor Licensee Event Report-(LER) Fil (NUREG-OI6I)

Exlublt I

~ Saluc Source

UNITSHUTDOWNS AND POWER REDUCTIONS 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 po'wer levels.

Each signi-ficant reduction in power level (greater than 2(Ffo 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 listed, as zero, the method of red'uction 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 significant power reduction.

Report as year, month, and day.

August i4. 1977 would be reported as 770814.

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

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend 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.

Self<xplanatoty.

When a shutdown extends beyond the end of a report period, count only the time to the end ot the report period and pick up the ensuing down time in the following report pericles.

Report duratibn of outages rounded 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 reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing on the report t'orm. Ifcategory H must be used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCliVG POWER.

Categorize by number designation INole that this differs l'rom the Edison Electric Institute tEEI) 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 MW ls 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 applicable reportable occurrence pertaining to the outage or power reduction.

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not'a reportable occurrence was involved.) If the 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).

SYSTEM 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.

COMPONENT CODE.

Select the most appropriate component I'lom 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 mal-function should be listed. The sequence of events, includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.

Components that do not fit any existing code should be de.

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

component designation is not applicable.

CAUSE Sc CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative fashion to amplify or exphin the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut ~

down or significant power reduction and the immediate and contemplated long term corrective action taken. ifappropri-ate.

This column should also be used for a description of the major safety 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 ot radioactivity or single radiation exposure specitlcally asso<<i-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'erence the shutdown or power reduction t'or tiu>

nJrfJt 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)alc lA L

r)

L 0

A J Q

Liccoscc Event Rcport 4 Co~

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Q Q

C)

)

O Cause &, Corrcclivc At:tion lo Prcvcol Rccurrcnce 121 780117 F

34.7 H

H/A L1C VALVEX Unit removed from service due to leak through from makeup 'plant causing high conductivity in all steam generators.

Returned to service 780119.

At 1005 power 780120.

I I': Forced S: Schedule)I Reason:

A-Ecluipn)ent Failure (Explaio)

D.hlaittlenance or Test C.Refueling D-Regulatory Restriction E-Opecaloc Training & License Iixamioation F-Administ ca live G Opccattol)al L)rur (I'.xplatn)

I I Other (Explairt) hlethod:

I-Manual 2.h(aoual Sera)n.

3-Ante)marie Scrato.

4-Other (Explato)

Exhibit G - Instructions I'or Preparation ol Data Entry 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 the report 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 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 completelyl.

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 significant power reduction.

Report as year, month, and day.

August i4. 1977 would be reported as 770814.

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

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche.

duled," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend 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.

Self<xplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end of the report 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 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'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INote that this differs t'rom the Edison Electric Institute IEEI) 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 MW is tilo 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 applicable reportable occurrence pertaining to the outage or power reduction.

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not'a reportable occurrence was involved.) If the 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).

SYSTEM 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.

COMPONENT CODE.

Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

using the followingcritieria:

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 ofevents, 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 8c CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated Iong term corrective action taken. ifappropri-ate.

This column should also be used for a description of the major safety-related corrective maintenance performed during the outage or power reduction inciuding an identification of the critical path activity and a report of any single release of radioactivity ur single radiation exposure specitically 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 reference ilie shutdown or power reduction for thii llarratlve.

(9/77

Docket No.

Unit Name Date Completed by Telephone 50~315 D

C.

C ok -

U it 1

2-

-78 R

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 Unit 2 Turbine Generator.'wo separate instances of acid entering the Condensate System during resin regeneration of the Demineralized Water Make-Up Plant forced a reduction in power while working to reduce Steam Generator conductivity.

SUMMARY

1/4 At the beginning of the month the unit was operating at lOOX power.

Unit load~was reduced to 45K due to high conductivity in Steam Generators which was caused by acid getting into the Condensate System while regenerating resin i.n the Make-Up Plant.

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 used to 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 hours0.0232 days 0.558 hours 0.00332 weeks 7.64044e-4 months and the Generator parralleled with the system at 2222 hours0.0257 days 0.617 hours 0.00367 weeks 8.45471e-4 months .

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

Reactor was critical at 1546 hours0.0179 days 0.429 hours 0.00256 weeks 5.88253e-4 months and the Generator parralleled to the system at 1852 hours0.0214 days 0.514 hours 0.00306 weeks 7.04686e-4 months .

The unit was shutdown from 1004 due to high conductivity in Steam Generators which was caused by acid getting into the Condensate System while regenerating resin in the Make-Up Plant Reactor was critical at 2326 hours0.0269 days 0.646 hours 0.00385 weeks 8.85043e-4 months .

Generator parralleled with the system at 0136 hours0.00157 days 0.0378 hours 2.248677e-4 weeks 5.1748e-5 months .

The unit was at 100K power at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months .

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

DOCKET NO.

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

Cook - Unit No.

1 2-10-78 B. 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 gland studs and the packing had blown out.

Installed new gland studs and repacked 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 pressure was 4 psig lower than the minimum.

Replaced leaking mechanical shaft seal and had pump retested.

DG-117A, AB2 diesel starting air compressor strainer valve leaked by.

Stem was badly bent.

Replaced valve.

Recorder MR-36, refueling water storage tank level recorder, indicated off scale on the high end.

The level transmitter ILA-950, calibration was found 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 high alarm condition.

The level of the tank was verified at 9.6 feet.

The mercoid instruments, providing the alarm functions, setpoints are adjusted to a low value (psi), the reset of the instruments require a large change of level.

The instrument was manually reset and correct operation of the alarm was verified.

C&I-3 C&I-4 The C02 protection for the 4KV room switch gear cable vault would not reset.

The alarm bell relay was found to be mechanically latched.

The relay required physically resetting.

Hazard 7 was retested and cleared the red light by opening the knife switch and reclosin'g the switch.

The reset push button then was depressed.

The control system functioned properly.

RRV-306, gas release trip valve failed to open as required by the control circuit.

A loose connection at the fuse in the control circuit had removed control power.

The fuse clips were tightened and the fuse reinstalled.

,Correct valve operation was verified.

DOCKET NO.

UNIT NAME DATE PAGE 50 - 315 D.

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 steps from the associated bank.

The signal condition module voltage was found to be greater than required, The module calibration was performed and correct indication returned.

CSI-6 CSI-7 CSI-8 DCR-340, steam generator blowdown isolation valve, limit switches were out of adjustment which prevented DCR-340 from remaining

open, The coupling 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 voltage on the drawer assembly required adjustment.

Rod position indication for control K6, remained at 129 steps.

The voltage from the RPI coils was verified as correct.

The signal con-ditioning module required recalibration.

Following calibration, correct control 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 as pressure within the line between RRV-287 and WD-166.

Following the cycling of RRV-287, operatio'n of RRV-285 was verified.

C&I-10 NLP-151, pressurizer level protection set I, indicated 6g higher than the remaining channels.

Mater was pumped through the equalizing line to completely fill the condensing pot and associated instrument line.

The indication of NLP-151 returned to within specifications.

AVERAGE DAILYUNIT POWER LEV

~

I7

~

DOCKET NO.

D C

Cook 2

DATE 2-9-78 CO'qPI ETED gY W. T. Gillet-t T~> EPHONE 616-465-5901 ONTH January 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net )

I 0

DAY AVERAGE DAILYPOWER LEVEL (M

We-Net

)

0 17 3

10 12 13 14 15'6 0

0 0

0 18 19 20 21 23

%5 26 27 28

'>9 30 31 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 NO DATE 2-9-78 COMPLETED BY W. T. Gillett TELEPHONE ~~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):

1118 1082 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 correlation and the improved thermal design procedure WCAP-8762 and WCAP-8567.

This Month Yr.-to-Date Cumuhtive

11. Hours In Reporting Period

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 (MWH) l 7. Gross Electrical Energy Generated (i%IWH)

18. Net Electrical Energy Generated (iiIWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Un!t Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months 744 0

0 0

0 (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):

INITIALCRITICALITY INITIALELECTRICITY COi~DIERCIALOPERATION Forecast 3/1/78 3/13/78 6/3/78 Achieved

UNITSI IUTDO'IVNSAND 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 Liccoscc Event Report 4 Cc Cl El

'e)

~AI/)'r CJ~

o ~

I) o O

Cause &Coffcclivc Aclh)o to Pfcvclll Rccllffcoce 0

771223 S

744 N/A zzzzzz Facility Operating License No.

DPR-74 was issued on Dec.

23, 1977.

Initial fuel loading commenced 'on Dec.

26, 1977 and was completed on Jan.

2, 1978.

Preparations for initial startup a'e in progress.

I: Foleell S: Schell<<lcll

(')/77)

Reason:

A.flluipolenl Failure (Explain) lib(aiotcnaoce oi Test C.Rer<<elhi(;

D.Ret,ulat ofy Rest rielion E-Operator Traioiol;& Lice>>se L'xaolioplioo I'-AlhninistIa I ive G Operation))I LIfor (I'.xplaio I I l.other {Expl:unl 3

hlcthod:

I.Manual

')-h(annal Scralo.

3-Autoolalic Scraol.

'I.Other {Explanl) 4 Exhibit C - Instructions for Preparation ol'Data Entry Sheets lor l.ieensec Event 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 the report 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 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 completely 1.

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.

NUiMBER.

This column should indicate the sequential num.

ber assigned to each shutdov n 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 assianed to each entry.

DATE.

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

Report as year. month. and day.

Auaust i4. 1977 would be reported as 770814.

iVhen a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Scne-duled," respectively, ior each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an oif.normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In general.

a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Seifwxplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end ot the report 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 of the total outage hours plus the hours the aenera.

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 be used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Caieaorize by number designation INoie that this differs t'rom the Edison Electri Institute tEEI) 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 form Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT

='.

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

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the tive part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for License Event Report (LER) File (iiIUREG4161).

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 appiicable (N/A)..

SYSTF&i CODE.

The system in which the outage or power reduction originated should be noted by the two digit code ot 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.

lV'OiMPONENT 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: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 described under the Cause and Corrective Action to Prevent Recur-rence column.

Components that do not fit any existing code should be de.

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

component designation is not apolicable.

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 signirtcant power reduction and the immediate and contemplated long term corrective action taken, ifappropri-ate.

This column should also be used for a description,ot the major safety. related corrective maintenance performed'during the outage 'or power reduction including an identificarion o!

the critical path ac;ivity and a report of any single release of radioactivity i/r single radiation exposure specitically associ

~

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

For long textual reports continue narrative on separate paoer anu reference tlie shutdown or power reductiun foi this liarrative.

a I

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE MAJOR SAFETY-RELATED MAINTENANCE 50 - 316 D.

C.

Cook - Unit No.

2 2-10-78 B. 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 to have been slightly scored during construction, Repaired seating surfaces.

612'levation personnel air lock door interlock was broken.

Replaced 2 interlock cables, adjusted interlock and had door retested.

Equalize line around RH-128E was broken.

Replaced 1/2" tubing for equalizing line.

M-5 A small fuel oil leak developed on a line from the fuel injection pump to the top of 0'8 cylinder on AB diesel.

Replaced fuel injection line and had it 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 shutdown cylinder 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 of AB diesel.

Also replaced leaking turbocharger discharge gasket and had engine 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 a

one 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 - 316 UNIT NAME""'""D. C-.

Cook - Unit No.

2 DATE 2-10-78 PAGE 2

MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1978 CD diesel crankcase relief cover on 85 front bank was leaking.

Replaced gasket.

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 the oil line and.fittings.

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ML18219D352

Text

SUBJECT:

SUMMARY

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