ML20077H804

Monthly Operating Rept for June 1983

ML20077H804
Person / Time
Site:	Cook
Issue date:	07/14/1983
From:	Gillett W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8308110318
Download: ML20077H804 (8)

Text

_

syy mwy

., t.w OPERATING DATA. REPORT

.~

a

~ ~

50-316 DCC:CT NO.

DATI _7-1-83 CO3t?LI ID IY W.T. Gillett TIL.I?HC.Ng 616-465-5901 c?rnnNGs ATus DONALD C. COOK 2

Nor:s 3, ug,3,=

JUNE, 1983

2. Repor-4-Pedad.

3411

3. U--- ad Th---! ?ower 0,1W:1:

1133

4. Ns=ep!:t= R::i=;(Cro=,1W ): -

1100 S. Desi;= I!:=:i=1 R::ing (Nec 11We):

1118

6. SM ::= Dependshte C27:d:7 (Gross $1We):

1082 T. Sis-- -

De-- d-ble t --- y (Nec 31We):

S. If C.::: es Oc=:in C:M y R::i:;s (1::=s Nc='..:: 3 Throu;h 7) Sise: Lss: Repor:. Give Re: sons:

i

9. Power Leve! To which Res=i==d.If Any (N : SDVe):

10. R== sons For ?# do:s.If Asy:

Cu. ::k:ive This btoath Y: <o-Cats 720 4,343 48,167 II. Hours In Repo:.is; ?=ied was C:i:imt 549.6 3,695.1 34.508.5

12. Nu..her of Hoc:s ? - or

~

~~

13. Re==ce R=se. e she:down Ho==

549.6 3,615.4 33,577.1

14. Ecur: Gene =:ce ca.Li==

0 0

0

15. U::i: R: serve Shutdown Ho==

1,851,461 11,858,599 108,122,830

16. Cross Th===:1 E==:;y Cen =:ed (31WM) 606,990 3.924,210 34.881.960

17. Cross Ee===!I=er:y Cen:=::d G.tWH1 586.771 3.790.093 33.629.885

13. Net E===i=1In ;y Gene =::d l'.GV~r-)

76.3 83.2 74.0

19. Unit Servi =.::::or 76.3 83.2 74.0 F

13. Uci: Av:IhhiE:7 :::or

21. Unit C: pad:f :"::: r (Usi::: >trc. Net) 69.9 75.3 80.7 74.1 79.3 69.0

. Unit C.spscity F:=or(Usin; CER.94t)

_4

• 1 1.4 12.7 l

23. Unit Forced Cunge R:te

24. Sh:: downs Schedu!cd Over Nec 5. ton:hs (Type. 0:::.: d Du=:icn of E:cht:

\\

~5. If Sh:: Down At End Of Report Period.Esti==:ed 0:te o(St::: o:

25; Units la Tes: 5::::s 1P=or to C:====!s! Ope:::fon1:

Fore =st Achieved 0

INITIA L C?.!T*CALITY

~

INITIAL I*.2CT?.:C; Y CO:47.:ERCIA:. 0? IRA 7 ON O

O PDR

i @" i 4

AVERAGE DAILY UNIT POWER LEVEL l

00CXET NO.

50-316 UNIT 2

DATE 7-6-83 T

COMPLETED BY Ann Might i

TELEPHONE (616)465-5901 l

4 Ii MONTH JUNE, 1983 k

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j

(MWE-Net)

(MWe-Net) 1 1085 17 1077 2

1086 18 1100 3

1086 19 1103 l

4 1083 20 1100

~

5 1082 21 1092 6

1084 22 1085 j

7 1073 23 934 8

1086 24 9

1074 25 i

i 10 1087 26 11 1070 27 12 825 28 13 1017 29 14 1078 30 15 1074 31 16 1066 INSTRUCTIONS On this format list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whola mecawatt.

DOCKETNO. 50-316 s,

UNITSiluTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 2 DATE 7-14-83 COMPLETEllllY B.A. Svensson REPORT MON 111 JUNE, 1983 TELEPilONE 616/465-5901 SHEET 1 of 1

,$3 3

Y Licensee

,E g ht Cause & Corecclive No.

Date k

gg s

3gse Event g,7 g]

Action to g-H aE g"c j ;p, g Repost #

un O Prevent Reciurence S

~

127 830611 S

0 H

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 78% due to low system demand. Reactor power re-turned to 100% on 830613.

128 830623 F&S 170.4 A&B 3

83-052/03L-0 ED INSTRU.

Reactor tripped due.to failure of vital instrument bus, CRID IV inverter.

Since the Unit had been scheduled for a two-week outage starting 830624, the decision was made to start the outage 4

one day early. The major reasons for the outage were to locate and plug the leaking tubes in steam generator No.

23 and perform ice condenser basket weighing. The Unit remained out of service at the end of the month.

I 2

3 4

F: Foiced Reason:

Meilnid:

Exhibit G -Insisuctions S: Scheduled A Equipment Failure (Explain) l Manual for Preparation of Data li-Maintenance of Test 2 Manual Scrans.

Entry Sheets foi 1.icensee C-Refueling 3 Aussunatic Scram.

Evens Repos II.liRI FileINUREG-D-Regulatosy Restriction 1 Other (Explain) 0161)

E-Operalor Training & License !!xamination F-Adminisisalive 5

G4)perallemal Essor (Explaint lixhibis 1 Same Somce 19/77) 11 Other (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS

~

INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report penod. In addition. it should be the source of explan-If category 4 must be used. supply bneicomments.

ation of significant dips in average power levels. Each signi-LICENSEE EVENT REPORT =. Reference the applicable ficant reduction in power level (greater than 205 reduction in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertammg to the outage or power reduction. Enter the Hrst four parts (event year sequennal should be noted, even thouah the unit may not have been shut down completely. For'such reductions in power level, report number, occurrence code and report type) of the 5ve l

the duratton should be listed as :ero, the method of reducuen part designation as described m item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns of course, smee should be used to provide any needed explanation to fully turther investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was mvolved.) If the outage or power reduction will not result m a reportable occurrence.

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

for that caisadar year. When a shutdown or si;;nificant power SYSTEM CODE. The system in which the outage or power reduction begms m one report period and ends m another.

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

~

an entry should be made for both report penods to be sure Exhi.. G Instructions for Preparation of Data Entry Sheets ott all shutdowns or sigmncant power reductions are reported.

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 signincant power reduction. Report as year. month. and day. August 14.1977 would be reported COSIPONENT CODE. Select the most appropnate component as ~70814. When a shutdown or significant power reduction from Exhibit I Instructions for Preparation of Data Entry begms in one report penod 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 followmg critieria:

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 B.

If not a component failure, use the related compontnt:

l reduction. Forced shutdowns include those required to be 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 mai-general, a forced shutdown is one that would not have been function should be listed. The sequence of events.includ-completed in the absence cf the cencition for which corrective ing the other components which fail, should be desenbed action was taken.

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

DURATION. Selfexplanatory. 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 j

end at the report period and pick up the ensumg down time events where a component designation is not applicable.

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

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum or the total outage hours plus the hours the genera-RENCE. Use the column in a narrative fastuon to amplify or vor was on line should equal the gross ho:.rs m the reportmg explain the circumstances of the shutdown or power reduction.

peri d.

The column should include the specine cause for each shut-down or siznificant power reduction and the immediate and REASON. Categonee bv letter designation in accordance contemplated long term corrective action taken, if appropri-cith the table appearing on the report form. If category H ste. This column should also be used for a desenption of the must be used, suppiy bnef comments.

ma or safety.related corrective maintenance performed dunna SIETHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER.

Categonze by number designation the entreal path activity and a report of any single release or radioactmty or single radiation exposure specifiesily 1ssoci-INote that this differs trom the Edison Electric Institute sted with the outage which accounts for more than 10 percent (EEI) dennitions of " Forced Partial Outage" and " Sche, of the allowable annual values.

duled Partial Outage." For these tenus. EE! uses.i change os For long textual reports contmue narrative on separate paper

.t0 31W as the break pomt. For larger power reactors. 30 5tW

.md reference the shutdown or power reduction ios this is f.e >m.ill a change to warrant expiartation.

narrative.

@!3

^

Docket No.: 50-316 Unit Names D. C. Cook Unit 2.,

Cmpleted By:

R. S. Isase Telephone:

(616) 465-5901 Date: 7/1/83 Page:

1 of 1 MONHILY OPERATING ACTIVITIES - JUNE 1983 Highlights:

The Unit entered the reporting period operating at 100%. There was one power reduction to 78% during the reporting period. The Unit tripped frm 100% power at 2137 hours0.0247 days <br />0.594 hours <br />0.00353 weeks <br />8.131285e-4 months <br /> June 23, 1983 and remained out of service the remainder of the month.

Total electrical generation was 606,990 MI.

Sumary:

6/11/83 Unit power was reduced to 78% over a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ranp starting at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />. 'Ihis reduction was due to low custmer demand.

6/13/83

'Ihe Unit was reloaded to 100% power over a 5-1/3 hour ranp.

6/23/83 The Unit tripped fr m 100% power at 2137 hours0.0247 days <br />0.594 hours <br />0.00353 weeks <br />8.131285e-4 months <br />. When Vital Instrument Bus IV failed. This was declared as the start of a planned outage that had been scheduled to start the following day.

6/24/83

'Ihe Beactor Plant was cooled down to Mode 4 by 0711 hours0.00823 days <br />0.198 hours <br />0.00118 weeks <br />2.705355e-4 months <br /> and -

Mode 5 by 1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />.

6/27/83 The Reactor Coolant System was drained to the la loop level by 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br /> and has remained in this condition the remainder of the reporting period.

Major reasons for the planned outage was to locate and plug leaking tube /s in #23 Steam Generator and to perform required Ice Condenser Surveillance.

Main Condenser halfs were out of service, one half at a time, for a total of 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> during the reporting period for identification and repair of circulating water leaks.

The Control Room Cable Vault "Halon" Fire Suppression System remained inoperable the entire reporting period. This system is being evaluated for required modifications. 'Ihe backup CO System remains 2

operable.

4 #

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 7-14-83 COMPLETED BY B. A. Svensson TELEPHONE

-(616) 465-5901 r

PAGE 1 of 2

!!AJOR SAFETY-RELATED MAINTENANCE JUNE. 1983 M-1 No. 4 boric acid transfer pump discharge pressure was lower than required. The pump impeller clearance was adjusted and the pump retested.

M-2 The ESW safety valve on the West CCW Heat Exchanger, SV-15-lW, was leaking by.

The valve was removed. The gasket was replaced and seating surfaces were lapped. The inlet piping was cleaned and the valve retested and reinstalled.

If-- [

The drain valve, MS-136-1, for No. 1 steam generator stop valve was j

eroded due to steam leakage. Replaced the valve and had the neces-sary NDE performed.

M-4 MRV-220, No. 2 steam generator stop valve had a broken linear bearing in crosshead. Replaced the linear bearing. Had the valve retested.

M-5 The No. 2 steam generator main steam protection channel instrument root valve, MPP-221V1, had a packing leak and the backseat was steam cut.

Replaced the valve and had NDE performed.

M-6 Motor operated containment isolation valve, ICM-321, the isolation from the West RHR pump to loops 2 and 3, had a packing leak.

Re-packed the valve and had it tested.

M-7 CVCS letdown regulating valve, QRV-162, operator diaphragm was leaking. Replaced the operator diaphragm and had the valve tested.

M-8 A leaking tube was identified in No. 2-3 steam generator. Plugged leaking tube, Row 1, Column 72..

C&I-l Turbine stop valve "C" position proximity switch for train "B" solid state protection system was stuck in the " closed" position. The switch was replaced and the stop valve was satisfactorily tested.

C&I-2 _ Intermediate range nuclear instrumentation high level trip channel II and power range N1 overpower trip lo range channel I status lights were " blinking in".

Replacement of solid-state protection system isolation circuit board, A505, corrected the. status light annunciation.

C&I-3 Critical control ~ room power inverter, 15KVA, failed. Two 25 micro-farad oil-filled capacitors and two 200 ampere fuses were replaced

.to restore:the inverter to operation.

O

, Ve

~

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 7-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1983 C&I-4 "W" motor driven auxiliary feedwater pump low suction pressure trip alarm was received for no apparent reason. A bourdon tube on pres-sure switch, CPS-245B, was leaking and was replaced. Calibration of the other two suction pressure switches was verified also.

C&I-5 Containment purge valves, VCR-101 through -106, (train A) closed spuriously. A defective E PROM integrated circuit chip was identi-fled and replaced on lower containment airborne' radiation monitors, ERS-2300 and -2400..

C&I-6 Containment-pressure relief fan, 2-HV-CPR-1, and isolation valve, VCR-107, (train B) tripped off/ shut spuriously during pressure re-liefs. E PROM integrated circuit chips on lower containment radia-tion monitors ERS-2300 and -2400 were changed out to correct the problems.

C&I-7 Control room instrument' distribution inverter (CRID IX) failed. A blown fuse and-a shorted capacitor were identified and replaced in the inverter. CRID IV then appeared to operate normally, but later the same fuse blew again. All diodes and SCR's in the inverter were checked. No problem could be found. The fuse was replaced and the inverter reassumed its load without further incident.

l J

w__

I e

eo W '

"",, INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 July 14, 1983 Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Cornission Washington, D. C.

20555 Centlemen:

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 June, 1983 is submitted.

Sincerely, L()./

u<

W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

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

R. C. Callen S. J. Mierzwa R. F. Kroeger H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski l

R. F. Hering i

J. F. Stietzel PNSRC File INPO Records Center Ilr