Text

Monthly Operating Rept for Aug 1983
	ML20078K358
Person / Time
Site:	Cook
Issue date:	09/14/1983
From:	Gillett W, Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8310190064
	Download: ML20078K358 (11)
	v • d • e

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R PDR

AVERAGE DAILY UNZT POWER LEVEL 00CXET NO.

sn_116 UtlIT 2

DATE 6-6-83 COMPLETED BY W. T. Gillett TELEPHONE 115d65-5901 M0 tith Auoust 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 985 17 1052 2

1047

.18 1055 3

1051 19 1051 4

1047 20 1044 5

1041 21 1052 6

1045 22 28 7

Ings 23 456 8

1046 24 9 -

1080 1066 25 665 10 1072 25 503 11 1056 27 1023 l

12 1066 28 1053 13 1061 29 1058 14 1063 30 1052 15 1056 31 1057 16 Inga l

INSTRUCTIONS On this format list the average daily unit pmaer level in PWe-Net for each day in the recorting month.

l Cemoute to the nearast whnla nac=wat*

DOCKETNo. 50-316 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME D.C.. cook - nnit 2 DATE 9-10-83 REPORT MONTil AUGUST, 1983 COMPLETED BY B.A. Svensson TELEPil0NE 616/465-5901 SHEET 1 Of 2 e.

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Licensee

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Causc & Canacctive

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Date g

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3 Action in

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130 830822 F

28.7 A

3 83-081/03L-0 ED INSTRU Reactor trip from 100% power due to failure of vital instrument bus, CRID II, inverter. The cause of the inverter failure was a shorted elec-trolytic capacitor. 'The entire in-verter was checked out orior to re-turn to service. The ice condenser inlet door surveillance test was per-formed while the Unit was out of ser-vice. The Unit was returned to ser-vice on 830823 and 100% reactor power was reached on 830823.

131 830825 F

9.3 A

3 83-081/03L-0 ED INSTRU Reactor trip from 100% pcwer due to failure of vital instrument bus, CRID II, inverter. The cause of the in-verter failure was a shorted electro-lytic capacitor. The inverter was checked out prior to return to ser-The capacitor failure is be-

-lvice.

lieved to be due to high ambient air i

2 3

4 F: Finceil Reason:

Method:

Exhibit G -Instructions S: Sthednical A Eigniement Failure (i.xplain) l-Manual fos Pseparatiini of Dasa ll-Maintenance of Test 2 Manual Scram.

Ent:y Sheets foi 1.icensee C Refueling 3 Automatic Scram.

Event Repost (1.ER) File (NtIREG-D Regula?4Hy Restriction Othet (Explain) 0161)

E-Operate.: l'eaining & License lixaminallon F-Administrative 5

G Operational Einor (Explain) lixhibit I - Same Somce 19/TI)

Il-Other (Explain)

UNIT SlfUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns during the in accordance with the table appearing on the report form.

report penod. In addinon,it should be the source of explan-If category 4 must be used. supply brief comments.

anon of significant dips m average power levels. Each signi-LICENSEE EVENT REPORT =. Reference the applicable ficant reduction in power level (greater than 20% 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 ) reportable occurrence pensining to the outage or power reduction. Enter the first four parts (event year. sequential should be noted, even though the unit may not have been shut down mmpletely. For such reductions in power level.

report number, occurrence code and report type) of the five l

the duranon should be listed as zero, the method of reducuon part designation as described in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correenve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG0161). This information may not be Cause and Correchve Action to Prevent Recurrence column immediately evident for all such shutdowns. of course, since should be used to provide any needed explanation to fully further investigation may be required to ascertain whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num-the positive indication of this lack of correlation should be bet assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begms in one report period and ends in another, an entry should be made for both report penods to be sure reduction onginated should be noted by the two digit code of all shutdowns or significant power reductions are reported.

Exhibit G -Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG 0161).

ber should be assigned to each entry.

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year. month and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814 When a shutdown or significant power reduction from Exhibit ! Instnu.tions for Preparation of Data Entry begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0161).

be made for both report periods to be sure all shutdowns using the following critieria:

cr significant power reductions are reported.

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

If not a component failure, use the related component:

reduction. Forced shutdowns include those required to b*

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

of an off-normal condition. It is recognized that some judg-ment is required in categorizmg shutdowns in this way. In C.

If a chain of failures occurs, the first component to mal-general, a forced shutdown is one that would not have been function should be listed. The sequence of events.includ-completed in the sbsence of the condition for which corrective ing the other components which fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur-rence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any existing code should be de-beyond the end or a report penod. count only the time to the signated XXXXXX. The code 777777 should be used for end at the report period and pick up the ensuing down time events where a component designation is not applicable.

in the following report periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fastuon to ampiify or for was on line should equal the gross hours m the reportmg explain the circumstances of the shutdown or power reduction.

Pen d The column should include the specific cause for each shut-down or significant power reduction and the immediate and REASON. Categorize by letter designation in accordance contemplated long term corrective action taxen. if appropri-with the table appearing on the report form. If category H ste. This column should also be used for a desenption of the trust be used.suppiy brief eumments.

maior safety-related corrective maintenance performed dunna the outage or power reductton including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categonze by number desig tation the entteal path activity and a report of any smgle release et radioactmty or single radiation exposure spect6eally assoet.

INote that this differs trom the Edison Electric muute sted with the outage which accounts for more than 10 percent t EEI) definitions of. " Forced Partial Outage" and " Sche.

of the allowable annual values.

duled Partial Outage." For these tenna. EE! uses a change of For long textual reports continue 7arrative on separate paper i

30 MW as the break pomt. For larger power reactors. 30 MW

.md reference the shutdown or power reduction for tnt i

is im bmall J ehanne to warrant explanation.

narrative.

l

I)OCKET NO.

50-316 i

UNITSilUTDOWNS ANI) POWER REI)UCIlONS UNIT NAME D.C. Cook - Unit 2 DATE 9-10-83 NEPORT MON 111 AUGUST, 1983 COMPLETED BY B.A. Svensson TELEPilONE 616/465-5901 SHEET 2 Of 2 "L.

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Y Licensee

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Cause & Censeclive 3

Action to No.

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,s,g Event g3 gO I-oE

E j ;y, Repost #

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6 131 temperatures in the area. The Unit Continu ed was returned to service on 830826, and 100% reactor power was reached on 830827.

4 1

2 3

4 F: Fmced Reason:

Meiluxt:

Exliibis G-Insimciiims S: Sclietf uleil A Equipmens Failme(Explaia) 1 Manual for Preparation of Data ll-Maintenance of Test

2. Manual Scram.

Entey Sheets for IJcensee C Refueling 3 Automatic Scrani.

Evens Repmt li.liR) File INtlRI:G-D Regulaimy Rest iction

-l Oilies (Explain) 01611

!!-Operaso Daining & License lixamination F-Attministrative 5

G Opesasional Eino IExplain) lisliibis I Same Somcc 19/77) 110 lier (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Tius report should describe all plant shutdowns during the in ac:ordance with the table appearing on the report form.

repon period. In addition. It should be the source of explan-If category 4 must be used supply brief comments.

ation of significant dips :rt average powet levels. Each signi-ficant reduction in power levet (greater than 20", reduction 1.lCENSEE EVENT REPORT. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pensimng to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequential shut down completely. For such raductions in power level.

report number, occurrence code and report type) of the five l

the duration should be listed as zero, the method of reduction pan designation as described in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correct 2ve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG016i). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since shoGd be used to provide any needed explanation to fully further investigation may be required to ascertain whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num, the positive indication of this lack of correlanon should be ber assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outsee or power reduction begms in one report period :sd ends in another,

~ '

reduction onginated sh' uld be noted by the two digit code of o

an entry should be mads for both report penods to be sure all shutdowns cr sigmficant pcwer reductions are reported.

Exhibit G -Instructions for Preparation of Data Entry Shests Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where

'DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814 When a shutdown or significant power reduction from Exhibit ! - Instructions for Preparation of Data Entry begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NCREG.0161).

be made for both report periods to be sure all shutdowns using the followmg critieria:

cr significant power reductions are reported. - --

8C 1

8e mpone dktly Wyed.

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

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

If not a component failure, use the related component:

reduction. Forced shutdowns include those required to be e.g., wrong valve operated through erron list valve as initiated by no later than the weekend following discovery component.

l of an off-normal condition. It is recognized that some judg.

ment is required in categorizmg shutdowns in this way. In C. If a chain of failures occurs, the first component to mai.

generst a forced shutdown is one that would not have been function should be listed. The sequence of events.includ-completed in the absence of the condition for which corrective ing the other components which fait should be described action was taken.

under the Cause and Corrective Action to Prevent Recur-rence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any existmg code should be de.

beyond the end of a report period, count only the time to the signated XXXXXX. The code 777777 should be used for end of the report period and pick up the ensuing down tune events where a component designation is not applicable.

l in the following repcrt periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fastuon to amplify or tor was on line should equal the gross hours in the reportmg explain the circumstances of the shutdown orpower reduction.

I Period.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and REASON. Categorize bv letter designation in accordance

' "***FI** *d I""3 ** #" "

"'**I'* **" " **N'"' II *FF'# F'I' with the table appearmg on the report form. If category H ate. Tlus column should also be used for a desenption of the must be used. supply bnet comments, major safety.rei:!ed corrective maintenance performed dunna the outane or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR the entical path activity and a report of any single release of REDUCING POWER. Categorue by number designation radioactivt:y or single radiation exposure spectriestly asscen.

INote that this differs trom the Edison Electric Institute sted with the outage which accounts for more than 10 percent iEEI) definitions or " Forced Pantal Outage" and -Sche.

of the allowable annual values.

duled Partial Outage." For these tenus. eel uses a change of For long textual repons continue narrative on separate paper

.0 MW as the break point. For larger power reactors. 30 MW

.md reference the shutdown or power reduction foi ttu>

is i.u small a change to wmar,t expiar.atioit.

narrative.

GuS

Docket No.:

50-316 Unit Names D. C. Cook Unit 2 Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date:

9/8/83 Page:

1 of 3 MONTHLY OPERATING ACTIVITIES - AUGUST 1983 Highlights:

The Unit entered the reporting period at 65% power with power being increased following a power reduction to 30% to permit repair of a steam leak.

100% power was obtained at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months 8/1/83.

There were two outages and tour minor load reductions during the remainder of the reporting period.

Details of these are in the Summary.

Total electrical generation was 749,030 MWH.

Summary:

8/2/83 The CD Emergency Diesel Generator was declared inoperable at 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months , during test, when it could not be paralleled to the auxiliary power bus.

Voltage could not be matched between the diesel generator and the auxiliary bus because of a failed fuse in the generator voltage circuit.

This was a special fuse and not immediately in stock.

Spare fuses were located and the diesel generator was again operable at 0028 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months 8/4/83.

While this diesel generator was declared inoperable, it was left in the automatic start condition.

It would have started and closed in on a dead bus which is it's designed " Black-out" requirements.

8/6/83 Unit power was reduced to 97% for testing of turbine i

valves.

Total time below 100% was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

8/13/83 Unit power was reduced to 98% for testing of turbine valves.

Total time below 100% was 3-3/4 hours.

i 8/17/83 The AB Emergency Diesel Generator was inoperable for a 15 hour1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months period for repairs.

The Low Pressure Carbon Dioxide Fire Suppression Systems were inoperable for a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 10 minute period while a failed solenoid coil was replaced.

This CO system is 2

common to both D. C. Cook Units.

8/18/83 The Low Pressure Carbon Dioxide Fire Suppression Systems were again inoperable for a 29 minutes period while a failed solenoid coil was replaced.

Again, this affected both Units.

Docket No.:

50-316 Unit Names D.C. Cook Unit 2 Completed By:

R.

S. Lease Telephone:

(616) 465-5901 Date:

9/8/83 Page:

2 of 3 8/20/83 Unit power was reduced to 98% for testing of turbine valves.

Total time below 100% was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The CD Emergency Diesel Generator was inoperable for a 7

hour period for repairs.

8/22/83 The Unit tripped from 100% power a t 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months when the power supply to one of the vital instrument buses failed.

The Reactor was returned to criticality at 2252 hours0.0261 days 0.626 hours 0.00372 weeks 8.56886e-4 months .

The Reactor tripped at 2339 hours0.0271 days 0.65 hours 0.00387 weeks 8.899895e-4 months due to high flux on the Intermediate Neutron Instrument N-36.

The trip point

.ot this instrument had been set at the wrong value (low) when it was reset from a previous test.

8/23/83 The Reactor was returned to criticality at 0107 hours0.00124 days 0.0297 hours 1.76918e-4 weeks 4.07135e-5 months .

The Main Turbine was rolled at 0221 hours0.00256 days 0.0614 hours 3.654101e-4 weeks 8.40905e-5 months .

The. Reactor and Turbine tripped at 0321 hours0.00372 days 0.0892 hours 5.30754e-4 weeks 1.221405e-4 months due to lo lo level in #22 Steam Generator.

The Reactor was returned to criticality at 0523 hours0.00605 days 0.145 hours 8.647487e-4 weeks 1.990015e-4 months .

The Main Turbine was rolled at 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months and the Generator was paralleled to the System at 0658 hours0.00762 days 0.183 hours 0.00109 weeks 2.50369e-4 months .

The Unit was loaded to 48% power by 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months and held at this level due to an indicated excessive quadrant power tilt.

The quadrant power tilt indication cleared and the Unit was loaded to 100% power over a 9-3/4 hour ramp starting at 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months .

8/24/83 The Control Room Fire Detection System was declared inoperable at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months due to failure to satisfactorily demonstrate that the detectors will perform as installed.

8/25/83 The Unit tripped from 100% power at 1610 hours0.0186 days 0.447 hours 0.00266 weeks 6.12605e-4 months when the power supply to one of the vital instrument buses failed.

The Reactor was returned to criticality at 2313 hours0.0268 days 0.643 hours 0.00382 weeks 8.800965e-4 months .

8/26/83 The Main Turbine was rolled at 0059 hours6.828704e-4 days 0.0164 hours 9.755291e-5 weeks 2.24495e-5 months and the Generator was paralleled to the System at 0131 hours0.00152 days 0.0364 hours 2.166005e-4 weeks 4.98455e-5 months .

The Unit was loaded to 48% power by 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months and held at this level due to an indicated excessive quadrant power tilt.

Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

R. S. Lense Telephone:

(616) 465-5901 Date:

9/8/83 Page:

3 of 3 The quadrant power tilt indication cleared and the Unit was loaded to 90% power over a 7-2/3 hour ramp starting at 1448 hours0.0168 days 0.402 hours 0.00239 weeks 5.50964e-4 months .

Loading was held at that level for testing of turbine valves.

8/27/83 The Unit was loaded to 95% power over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp starting at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months and held at that level for placing the reheater coils in service.

The Unit was loaded to 100% power over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp starting at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months and remained at that level the remainder of the reporting period.

Condenser halfs were out of service, one halt at a time, for a period of 30-3/4 hours during the reporting period for the identification and repair of leaks.

The Control Room Cable Vaul' Halon System remains inoperable as of 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on 4/5/83.

The Backup CO Sys for those times as stated in the Sudary. tem remains operable except Fire Watch's were posted during these times as required.

r DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 9-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE AUGUST. 1983 M-1 Containment spray system hand-operated valve, CTS-121E, had a body-to-bonnet leak. Replaced the bonnet gasket.

C&I-l Steam generator #3 blowdown sample valve, DCR-303, required replacement of defective piston and base plate o-rings to stop a control air leak.

C&I-2 Emergency diesel generator, 2AB, could not be tripped from the pushbutton stops or the "HEA" trip, and had to be shut down from the local p'ull knob. Asco solenoid valve, SV-6, diesel stop solenoid had an open-circuited coil. A replacement asco solenoid was installed. The diesel trip was verified from both the control room and local pushbuttons. The Worthington pneumatic control station operation was also verified.

C&I-3 Emergency diesel generator, LAB, "overspeed device failure" alarm was received. Relay #3 in box PM-4001, which monitors loss of power, had a shorted coil. Replacing the relay and resetting the alarm corrected the problem.

r l'

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I a

h KINDIANA & MICHIGAN ELECTRIC _C0hfPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman. Michigan 49106 (616) 465-5901 September 14, 1983 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 Unit 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of August, 1983 is submitted.

Sincerely, pf/

w. G.

mith, Jh Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Micrzwa R. F. Kroeger H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering g

J. F. Stietzel PNSRC File t

INPO Records Center I l

.

ML20078K358

Text

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