ML20082S895

Monthly Operating Rept for Oct 1983

ML20082S895
Person / Time
Site:	Cook
Issue date:	10/31/1983
From:	Might A, Peak G, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8312150048
Download: ML20082S895 (8)

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-s-OPERAT:NC DATA REPORT

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DCC:C NO. _50-316 DA7I 11-3-83 CO.':.*! IIO 7.Y Ann Mi nh+-

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c???.ATING S ATUS No::s r w n al a c c n nie 9

1. Uni:Nasse.

October 1983

2. Repor:Lv ? dad.:

3411

3. I.! =nsedTht:=21?swer(SiW:1:

1133

4. N:=eplat'= R:d. ; (Cross a:We): _ 1100

5. Desi;2 21e== =! R::ia;(Nec 51We):

1100

6. S'- :-s=== Depend:hte C27:ci:y (Cross SIWE):

1060 T. Siaxi--- Dep:.=d:h!= C:.p:=d:y (Net MWeli

8. If Ch:::::s Oe=rin C:p:=i:y R::i=;s (It==s Numhu 3 Th cq.h 7) Sic = Las: Rep =::. Give R::::r.s:

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9. ?ower !. eve! To W!d+. R=r:d= d. If Any (N:: MWe):

10. R= sons For R..: -: dons.!f Asy:

711s Mor.:h Y: <o.Osc Ce==l:dw 745 7296 91.1?n

11. Hoe:s != 3:;o.!s; ?:ded 357.3 6001.0 36.814.6

12. Nu=her Of Hou:s R::::ce Was Cdd=1 0

0 0

13. Rec::r R:sa:ve Sh::down E==

357.3 5902.5 35,864.2

14. Ho=s Cc= -*ar On I.!=,

0 0

0

15. U:!: Rese:ve Shutdown Ec=

1,188.]El 17,659,7 9 I L 6)),??2 lo. Cross The E==:;y Ce===: d (Mwg

17. Crosr.IIe=:i=!Ine::y Gene =:=d (MWM) 388,660 _

6,341,160 37,298,910 375,062 6.120,270 35,960,062

13. Net E!==:i=1I:=;y Cese=:::: C.tWE) 73.6 48.0 80.9

19. UWt Servi = F:: or 48.0 80.9 7.$. 6 F

20. Uni: Av:EshiE:7 :ctor 9#*b 79.1 70.3

!. Uni:C:: sci:7 ::::r(Us!=:MDCNet)

F 45.8 76.3 69.1

22. Unit Cacacity F:::or (Usin: DER.'let) 52.4 7.8 13.1

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23. Unit For::d Ou::ge Rate l

24. Sh:tdowns Scheduled Over Nx: 6 Mon:hs (Type. D::e. :r.d D=:fon af I:ch1:

/ /) k Refuelirxr mtnan eheanina fnt-4 1_na

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11-7-84

5. If Sh : Down A End Of R=; ort ? :iod. Esti: ::ed D:te of 5ts:=p:.

i 25' Units la Tes: 5:::v$ IPrior to Ce::== :!:I Oper:: font:

Fere=st Achieved INIT:ALCRIT CAIJTY INITIAL E:.ECU.:C;~Y CO.*.i.'.t E?.C:A:. O?!?.ATION I

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AVERAGE fAILY UNTT POWER LEVEL 4

• C0CKE'T NO. mn_116 UNIT 2

DATE ll-1-83 COMPLETED BY Ann Miaht TELEPHONE (616) 465-5901 MONTH october,1983 DAY AVERAGE DAILY POWER LEVEL -

DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net)

I 1r16 17 2

1082 18 3

1076 19 4

1076

'20 5

1082 21 6

1077 22 7

1078' 23 8

1073 24 9'

1087 25 j

10 1088 25 11 1091 27 12 inoo 28 13 1073 29 14 1027 30 15 545 31 l

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INSTRUCTIONS On this femat list the average daily unit power level in MWe-Net for each day in the reporting month. Comoute to the neeraM h h

DOCKET NO. 50-316 _

ilNIT SilUTinOWNS ANI) POWER REDUCTIONS UNIT NAME D.C. Cooit - Unit 2 11-14-83 I)ATF COMI'LE1ED BY B.A. Svensson REPORT MONTil OCTOBER. 1983 i

616/465-5901 TELErl ONE PAGE 1 of 1 "L

Cause & Corecceive

.E E 3

}g$f Licensee E3, 5

Evens F?

E-3 Attism so No.

Dale k

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jis Repene #

'E O O

Prevens Recmrence 6

Q 135 831015 F

387.7 A

1 N.A.

CC HTEXCH Started power reduction at 0849 hours0.00983 days <br />0.236 hours <br />0.0014 weeks <br />3.230445e-4 months <br /> due to indication of increased steam generator primary to secondary leak-age. Reactor power was held at 40%

for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to observe the trend in the leak rate. The leak-age continued to increase and the Unit was removed from service at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on the same day. As a result of Helium leak testing and Eddy Cur-rent testing, two tubes were plugged in Steam Generators 21 and 23 and one tube in Steam Generator 22.

The re-pair work has been completed. At the end of the month the RCS filling and venting was in progress.

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Methuti:

Exhibis G-Isistancliinis 1:: Fosces!

Heason:

l S: Solieduled A liiguipment Failme(Explain) 1 -Manual for Psepasation of Data II. Maintenance o( Test 2 Manual Sciam.

Eni:y Slicens fin 1.icensee C-Refueling 3-Aulomatie & sam.

Event Rep w II.1:RI FileiNtlRI.'G-D Hegulato y Restiiction Othes (lixplain) 0161) li Opesato l'saining & License lixamination F.Atiministrative 5

INhibis 1 Same Somce G Openaltimal Lour (lixplaint l'8/17) 11 Other (lisplain)

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l UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS T1us report should desenbe all plant shutdowns during the in accordance with the table appearms on the report form.

report penod. In addition,it should be the source of explan.

If category 4 must be used. supply brief comments.

ation of sigruficant dips in average power levels. Each signi.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT z.

Reference the applicable 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 />)

MPortable occurrence pertaming to the outage or power should be noted, even though the unit may not have been reduction. Enter the Erst tour parts (event year, sequenna!

shut down completely. For such reductions in power level, fePort number, occurrence code and report type) of the nye l

the dursuon should be listed as zero, the method of reduction part designation as desenbed in-Item 17 of Instruccons for should be listed as 4 (Other), and the Cause and Corrective Preparauon of Data Entry Sheets for Licensee Event Report Action to Present Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause and Correcuve Action to Prevent Recurrence column immediately evident for all such shutdowns.of course, smee should be used to provide any needed explanation to fully further investiption may be required to ascertam 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 secuential num, the positive indication of this lack of correlation should be ber assigned to each shutdown or ugnincant redus' tion in 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 begins in one report period and ends m another.

an entry should be cade for both report penods to be sure reduction onginated should be noted oy tne two digit ecde or.

all shutdowns er sigmncant power reductions are reported.

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

ber should be assigned to each entry.

Systems that do not fit any existing code should be designs.

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 appiicable.

of each shutdown or significant power reduction. Report as year. mcnth, and day. August 14.1977 would be reported COMPONENT CODE. Select the most apptcpnate component as 770814 When a shutdown or significant power reducton from Exhibit i. Instrucuens for Preparation of Data Enm begms in one report pened 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 stiutdowns using the following entiena:

or signincant 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:

reducuon. 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 mai.

pneral, 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 wiuch fail, should be descr: bed 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 ot a report penod, count only the time to the signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensuing down time events where a component designation is not applicaole.

in the following report penods. Report duration of outays 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 narranve fastuon to ampitfy or tot was on line should equal the pross hours in the reportmg explain the circumstances of the shutdown orpower reducuen.

Period.

The column should include the specific cause for each shut-

• n f gni C2nt pnwer mduction and the immediate and REASON. CateI'mee by letter dest 8 nation in accordance contemplated long term corrective acnon taken if appropn-with the table appearing on the ' report form. If category H ate. This column should also be used for a desenption of the must be used. supply brief comments.

d elated amM mum WW de METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identincation ot REDUCING POWER. Cateponee by number desgnation the enusal path acavity and a report of any single release or radioactmty or smgle radiation exposure speettiesily associ.

I o,e that this differs r~ rom the Edistm Electne Institute sted with the outage which accounts for more than 10 percent N

IEEI) definitions of " Forced Partial Outase" and " Sche, of the allowable annual values.

duled Partial Outage." For these tenus. I El uses 4 shange ot' For long textual reports eontinue narrative on separate paper

.t0 MW as the break pomi. For tryer power reactors.30 MW and reference the shutdown or power reduenon foi ini, is tuo small a change to warrant esplanation.

narrative.

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Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

G. J. Peak Telephone:-

(616) 465-5901 Date:

11/8/83 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - OCTOBER 1983

, Highlights:

The. Unit entered the. reporting period at 100% rated thermal power.

Power was reduced to 40% to observe an upward trend in the. primary to secondary leakage which had increased during a moderator. temperature coefficient test.

The leakage continued to increase and the Unit was removed from service.

Five leaking Steam Generator Tubes were identified and plugged (2 in #21 S/G, 1 in #22 S/G and 2 in #23 S/G).

As the reporting period came to an end, the Reactor Coolant System had just been filled and vented in preparation for Reactor startup.

Summary:

10/1/83 Reduced power to 99% for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period to test the Main Turbine Control Valves.

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10/3/83 Began reducing Reactor power at 1% per. hour at 1543 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.871115e-4 months <br /> in order to comply with Tech Spec 3.0.3 due to a discrepancy in the over temperature Delta T setpoints.

The setpoints were determined to.be within the allowable limits and the power reduction stopped at 96% at 1712 l

hours.

The Unit was returned to-100% power at 2006 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.63283e-4 months <br />.

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The Control Room Radiation Monitor (R-1) was inoperable from'1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on 10/3 until 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> on 10/5.

10/8/83 Reduced power to 98% for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period to test the Main Turbine Control Valves.

10/14/83 Reduced power to 95% at 0358 hours0.00414 days <br />0.0994 hours <br />5.919312e-4 weeks <br />1.36219e-4 months <br /> for a moderator temperature coefficient test.

10/15/83 ' Reduced power to 40% at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> to observe an upward trend in the primary to secondary leakage.

The leakage continued to increase and the Unit was removed from service.

The Reactor and turbine were tripped at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.

.10/16/83 Mode 4 was entered at 1146 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.36053e-4 months <br />.

The East Motor Driven Auxiliary Feed Pump was inoperable for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period because the Low Suction _ Pressure Trip was locked in.

10/17/83 Mode 5 was entered at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />.

10/30/83 Reactor Coolant System filled and vented at 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br />.

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Docket No.:

50-316 Unit Nam 3:

D. C. Cook Unit 2 Completed By:

G. J. Peak Telephone:

(616) 465-5901 Date:

11/8/83 Page:

2 of 2 The Control Room Cable Vault Halon System remained inoperable the entire reporting period.

The backup CO System remains operable.

2 The Control Room Fire Detection System remained inoperable the entire reporting period.

Hourly fire patrols are being made behind the Control Panels.

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DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465'-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE i

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OCTOBER. 1983 M-1 The' pressure instrument root valve for #4 steam generator, MPP-241V1, had been injected with Furmanite to seal a body-to-bonnet leak. Replaced the valve and had necessary NDE per-formed.

M-2 Pressurizer power-operated relief valves, NRV-151 and 152, were leaking by.

Replaced the stem, plug, seat, gaskets and packing of NRV-151. Lapped the plug to the seat and replaced the gas-kets and packing for-NRV-152. Had both valves tested.

1 M-3 Auxiliary feedwater isolation valve, FM0-222, was leaking by.

Remachined the plug, lapped the seat and repacked the valve.

Had the valve tested.

M-4' Testing of the steam generators revealed leaking tubes. Plugged two tubes in #21, one tube in #22 and two tubes in #23 steam generators, utilizing Westinghouse mechanical plugs.

4 C&I-l Pressurizer pressure instruments NPP-152, 153 and NPS-153 were checked and found to be out of specification. After recalibra-tion, pressures agreed within 20 psig on all instruments.

. C&I-2 Critical control room power inverter failed when a filter ca-pacitor short-circuited in service. Replacement of the capac-itor and a fuse restored the inverter to operability.

L C&I-3 The gauge protector was not working properly on the low suction pressure trip device for the east motor-driven auxiliary feed pump. The gauge protector was repaired and calibration of the pressure switches was performed. The gauge protector worked for a day until it stopped passing pressure again. The gauge saver was then replaced and recalibrated.

C&I-4

. Reactor coolant system loop 3 cold leg narrow range spare re-sistance-temperature detector (RTD) failed.. The RTD was re-placed in accordance with 12 THP 6030 IMP.047.

C&I-5 Unit vent iodine radiation monitor, ELS-2503, stuck in its

" check-source" mode of_ operation. After rebuilding tee check source mechanism, channel ERS-2503 was demonstrated to be op-etable.

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PA'GE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1983 C&I-6 Steam generator #2 stop valve air operator for valve, MRV-222, developed an air leak at _its diaphragm. The quick-release valve diaphragm and gasket were both replaced to correct the leak.

C&I-7 Control rod drive motor generator "2N" circuit breaker relay timer, 62-0V-G2, was found to be improperly timing. The relay was replaced and was set to time out at 5 seconds per Westinghouse Tech. Manual Specifications.

C&I-8 Reactor coolant pump #3 lower radial bearing RTD (resistance-temperature detector) was replaced with a new unit. The cable which feeds the P-250 computer had been switched over to the spare RTD when the normal RTD failed. This cable was reconnected to the normal RTD after replacement.

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,,, IN0 LANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901

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~ November 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 October, 1983 is submitted.

Sincerely, W

A?

W. G. Smith, Plant Manager WGS:ab Attachments cc:

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

R. C. Callen 1

I S. J. Mierzwa AI R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center

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