Text

Monthly Operating Rept for Jul 1983
	ML20024F102
Person / Time
Site:	Cook
Issue date:	08/02/1983
From:	Might A, Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8309080232
	Download: ML20024F102 (9)
	v • d • e

-

I INDIANA & MICHIGAN ELECTRIC _ COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 August 12, 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 July, 1983 is submitted.

Sincerely, CM, M

7/

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. Micrzwa R. F. Kroeger H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INP0 Records Center 8309020232 830002

{Ie

)

PDR ADOCK 05000316 y

R PDR 1 \\

r.=-

o CPER.t"":NC DATA hJ.?OR.T 5'0-316'

~~

D C C K.I T N O.

DATI _f>-P-83

~

CO5 ?L.~.~ID EY

.A.

Micht TILI.?HCNE (NMR 4901 C???r'NG 5 ATUS Not:5 DONALD C. COOK 2

1. Unic Ns==:

JULY 1983

2. Reporns; ?s:fod.:

3411

3. I.I: = sed Th--! ?ower (5 W:::

1133

4. N:=eplais ?2:in;(Grau 5 W ):

11UU

5. Desi;= Ee=:i=1 R::in;(Ne.51We):

l100

6. Sf- "mu:= Dryend:ble Cap:i:f (Gross 51We):

1060

7. Sis.xi===: Dep:=d:h!= C=== f (Nes 5!We):

S. If Ch:=;es Oc=:!n C:p:=i:y R::is;s (1::=s Nc::h::3 Th:ou;h 7) Sic:: L:s: Repe :. Cive R:: sons:

ITEM 6 CHANGED FROM 1118 TO 1100. ITEM 7 CHANGED FROM 1082 TO 1060 DUE TO CHANGE IN THERMAL POWER. ALL CHANGES ARE INCLUDED IN THE YEAR TO DATE AND GUMULATIVE COLUMN.

9. Powee Leve!To Whi:h R= sci ed.If Any (N : 51We):

10. R== sons For R...ei::ior.s.lf Asy:

This Month Yr.4o.Date.

Cu==I::ive 744 5087 48,911

11. Hou:s != Repo:.in; ?:: icd 535.1 4230.2 35.043.6 1*. Nu=her Cf Hou:s ?.==: rwas Cri:i::.1 0

0 0

13. Re::::r Rese.'e Sh::down Hon::

530.5 4145.9 34,107.6

14. Eour: Gee =: e ca.LI:=

0 0

0

15. U..!: R: serve Sh :dowu Ho==

1.711,373 11,858,599 109.834.203

16. Gr:ss The:=.! E==:;y Ce===:ed (5:WH) 543.510 4.467.720 35.4?E.470

17. Cross Ee==.=1I: ::y Ce===:ed I,MWH) 523,453 4,313,546 34.153.338

13. Net Ee==i=12 : ;y Cen==::d (5 W'd) 71.3 81.5 74.0

19. Uni: Serri::.::::or 71.3 81.5 74.0

20. Uci: Ar:ilshi!I:y F:c:or 66.4.

80.0 70.0

1. Unit C::scity !"::::r (Usi=; >!DC Ne:)

64.0.

77.1 68.9

. Unit Capeity.::::::(Usin; DIR.4ett 0

1.2 12.6

23. Uni:.cor:ed Cu::ge R::e l

24. Sh:: downs Scheduled Over Nec 5 Mc=:hs (Type. 0:te.:nd Oc=:fon of I:cht:

~ - - ~ -

25. If S.v:: Down A Ind Of Reper: ?eriod. I:ti==:ed D:te of 5:2 ::p:

.25' Units :n Tes: S :::s IPnor to C:====is! Ope =: font:

Fore =st Acafeved INIT:A:. CRIT *CA LITY INmAL I:.ICTa:C: Y Co?.t!.:IF.C:A:. CPEnA 7:CN 7

ADJUSTED BACK TO 1-1-83 DUE TO CHANGE IN ITEM 7 tui-i I

e

_,......,...,m,,

,-,,. _.- _, _,._ m

AVERAGE DATLY URlT POWER LEVEL DOCKET NO.

50-316 UNIT 2

DATE 8-2-83 COMPLETED BY A. Might TELEPHONE (616)465-5901-MONTH JULY, 1983 DAY AVERAGE DAILY POWER LEVEL DAY (MWE-Net)

AVERAGE DAILY POWER LEVEL (MWe-Net) 1

~

17 1041 2

18 1046 3

~

19 1049 4

20 1060 5

21 1048 6

22 1049 23 1027 8

~

24 1045

~

9

~

25 1060 10 631 25 1081 11 958 27 1053 12 1064 28 1035 13 1059 i

29 1039 r

14 1050 30 1011 15 1040 l

31 373 16 997 INSTRUCTIONS i

day in the reporting month.On this format list the average daily unit p l;.

Com0ute to the nearest whnla macawatt.

I)OCK E I' NO. 50-316 IlNil SiltlIDOWNS AND POWER HEDirilONS D.C. Cook - Unit 2 UNII N AhlE DA'IE 8-12-83 JULY, 1983 COkiPI EIED Hy LA Svensson 616N6M9D1 HIPOlt'I'AION~lli

.I El LPilONE SHEET 1 of 1 SE 3

, b' I itensce

$'s,,

"L Cause & Coniessive No.

D.He 3g M

.g g y

!!veni g vg o.1j Atis,,n so a

$5 5

jdig itepost 38 EO l' sevens Hecuncaic 6

128 830623 F&S 213.5 A&B 3

N.A.

ZZ ZZZZZZ The unit entered the reporting period in Mode 5 with the RCS at hal.f-loop.

The reason for the outage was to plug a leaking tube in S/G No. 23 and per-form ice condenser basket weighing.

One leaking tube was plugged at lo-cation Row 1, Column 72.

The tube was plugged by Westinghcuse using a mechanical type. plug. The unit was returned to service 830709 and brought to 100% power on 830711.

129 830731 F

0 B

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 30% to per-mit repair of steam leak on the right inner turSine control valve below seat drain line. Reactor power returned to 100% 830801.

1 1

2 3

l Il linercil Reason:

kleilual:

1:minhis G. Insein. ii.ms S: S heilnicil A l eguipn.cs.: 1 aihne (l'.mplain)

I klannal los INep.n ation nl Dasa 11 hiainicnance os Test 2 klanual Scrani.

1 nasy Sheess hu Iisemce C Hefncling

1. Antum.itic Leans.

I vens Hep us il l'HIl ale INilHI G-D Hegulaenay Hestanttiini l Oaha (l.nplain) 0161)

ILOpesanos I'saining & litenw l~xamination i

I Ailnunassiaer<c 5

G Opesalinnal I a nos ll%plas:in i sinbit i Same Somic p8/l/)

11 Ot hes libplaini

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report snould des =be 21! ;!2nt shutdowns dunni me a n::r:ance A:s me :::le 2 :e2:=g en me repor fo rm.

report penod. In addit:on. It should :e the sour:e of explan.

If ntegory 4 must be used. sup:iy b :ef ::mmen:s.

anon of sigmd an: dips m 2verage power leveis. E2:n nz:u.

S:2nt redu:non m power tevel (pester 82n M reduction LICENSEE EVENT REPORT =. Referen:e 2e app!::2b!e c 2ver22e da!y power teve! for me :re:ecinz 24 houn; apen2:ie ::unence pen 2==2 o de utage or powe-ecu ncn. Ente *he i-n four ;2ns 'even,n. 2equenn2.

snould be noted, even $cu:h de amt may no't have :een shut down completely. For such reduenens a power ; eve!.

repor: number. o::unence : de and report type) of :ne dve l

~

tne durst:on snuuld be listed as :ero.de medcd of teduction part denpation as des = bed d item 17 of Ins::uencns f:r snould be listed as 4 (Oder) 2nd de Cause 2nd Cctre:nve

?":2nna of Data Entry Sheets for L::ensee Event Repc::

A;:icn to Prevent Re:unence :clumn shotdd expism..The (LER) Ele (NUREG4!61). Tha mformanen may act :e Cause ma Corre:nve Aenon to Prevent Re:unence column immedia:ely ev: dent for 2d such shutdowns. of :ourse se:e should be used to provide any needed explananon :o fully furtner.nvestg2 tion ::'ay be requ::ed to as ertzm

nether er desence the circumstances of the outage er power redue:icn.

not 2 aport 2cle cc:urrence was involved.) !: the outage or power redu;::on wtil not result in a repor:2:le ec:urrence.

NU5tBER. T us ::iemn should ind!=te the sequential num.

the poutive mdt:2: ten :( 8:s ::ck ci :orreianon should :e er asugned to each shutdown or ugmneant reduction m power noted as not applicab:e G A).

for $2t :21endar vear. When a snutdown or ngnid:2nt power SYSTE31 CODE. The system in w..::n :ne outage or power a

redue: ion beg:ns in one report period 2nd ends m 2nother.

on ongnated M be noted :y the two dp ecde m.

Ie 2n entry should be made for both repon penods to be sure cx ucit G. Inst:uences for Preparanon of D2ts catry 2 net:5 n! snutdowns or s:::udant : owc: reduenons are reported.

or Lcensee Event Re: t (LER) :He GUREG4 !61).

Unt:12 unit has 2:Seved its h::t pone:;ene:2 tion, no num-ber should be assiped to es:n entry.

Systems :nat do not fi: 2ny existmg :cde shouic e deup2-ted XX. The :oce ZZ sucu!d be used f:r dose events where DATE. This column should = dica:e the date of de start 2 system is not a:pli: sole.

of each shutdown or s;plS ant power redu:non. Re: ort

.s yest. month. 2nd day. Aupst 14.197 would be repor:ed C051PONENT CODE. Sele:: de mes: 2:prc priate.omponent as MCS14. When 2 shu:down or sig:unc=t power reduenan from Exh:bst i Ins::uenons for ?:e:2:2nen of Data Ent.m bepts m ene report pened 2. d ends m 2nother. an entry should Sheets for Licensee Even: Report (LER) Fde(NUREC41615.

be made for both report peneds to be sure all shutdowns usmg the foi!cwing entiena:

or ug sE;2nt power redu:nons are reported.

TYPE L se "F" or "S" to indicate e:ther "For:ed" or " Sche.

duled." resce:nvely, for each shutdown or sipificant power B.

If not 2 :cmeonent f2 dure, use de re:2ted ecm:enent.

redu:non. Forced shutdowns m:iude those required :o be e.g.. wrong valve operated throup enor: !ist valve as nl:iated by no 12:et than the weekend following dise:very ecmeonent.

of an off normal :endinon. It is re:cgni:ed that some judg.

ment :s required in :stegonz=g shutdowns in this usy. In C.

li a chain of failures occurs. the Ers ecm:enent :o mai.

gener21. 2 forced snutdown is one that would not have been fun::fon should be listed. The secuence of even:s.melud.

ecmpleted in de absen:e of the ::ndition for which :crie::ive ing the other : mponen:s wh::h fail. should be des:nbed scuon was taken.

under the Cause 2nd Corre:nve Acton :o ?: event Re:ar.

rence column.

DURATION. Self-explanstery. When a shutdown extends Components that do not at any ex:snns : ode should be de.

.:eyond the end of 2 report penoc. count only t_,e t:=e to the upated XXXXXX.,the code ZM., snocad be used :.or end of the report penod 2nd pick up the ensumg down n=e events wnere 2 component desapation :s not 2ppii:2cle.

m the fudowme recort :enods. Re ort duration of outages rounced :u tne nearest tentn uf 2n hour to fae:!itate summanen.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the geners-RENC,.. L.se de ;clumn in 2 narranve issbaon :o ampitfy or

or was un h.ne should equal the pcss ho'sts a de repor:=g expizin de :camstances of:he shutdown or power recu:ncn.

pen d.

The column should m !ude the spec:d: :2use for each snut.

down or sicin:2nt power reduenen and de ;mmed2te anc REASON. Categonee 5,etter w,engnattun in accordan:e with the taoie a:pe:rmg on the report form. If :stegory H eentem:isted lunz :erm c rreenve scn.en taken. if appreen.

a 2te. uns emumn snould also be used :or 2 desenpt:en of:ne must be use. su:piy bne; eumments.

maict safety.re!s:ed corre:nve mamtenan:e performec funna alETHOD OF SHUTTING DOWN THE REACTOR OR e outage or ;cwn adu:n= indumny 2n :denn6cnon y REDUCING POWER. Cate;unze :iy number denznsuun

'h'. =t:.21 patn 2;nvity 2nc 2 report or any sinpe re: esse er rac:ose:mt) ur smzie radianon ex:csure see.tnastly asse :.

I%te that this difrers trom the Edison E!e::n: Insntut, ated with the outage wrucn ae:ounts for more inan 10 :e.en:

tEEI? denmtions of " Forced Partt:1 Outare" and "Sene.

di de li!o*2Ee 2nnu21 v21ues.

uied Partial Outap

For these terms. hEl uses 4.hange or For !ong textual repens contmue narrative an se:2rste : 2:er

.t0 Siw 2s the break ;wnt. For taree power reactors.30 SlW and :::eren e the shutdown or power tscu. nun u.i

. i>

.s t..

3rnatl J.hange to wanant nplanattua.

narranve.

w --

~~

~ ~ ~

n.

~_.

Docket No.:

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

R.

S. Lease Telephone:

(616) 465-5901 Date:

8/5/83 Page:

1 of 3 MONTHLY OPERATING ACTIVITIES - JULY 1983 Highlights:

The Unit entered the reporting period in Mode 5 with the RCS at half loop operation.

Major reasons for the outage was to locate and plug a leaking tube in 323 Steam Generator and perform required Ice Condenser Surveillance.

The Unit was returned to 100% power operation on July 11.

There were-six minor load changes and one significant load change during the remainder of the reporting period as detailed in the summary.

Total electrical generation was 543,510 MWH.

Summary:

7/1/83 Vent Stack Iodine Radiation Monitors R-31 and R-32 were inoperable for a 6h hour period while the Tritum Collector was relocated.

7/5/83-Vent Stack Gaseous and Particulate-Radiation Monitors R-25 and R-26.were inoperable for a 29 hour3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months period starting at 1029 hours0.0119 days 0.286 hours 0.0017 weeks 3.915345e-4 months while the sample pump was replaced.

.The Reactor Coolant System was filled and vented by 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months .

I.

7/7/83 Reactor Coolant System Heatup was initiated and the Unit entered Mode 4 at 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months .

7/8/83-The Unit entered Mode 3 at 0229 hours0.00265 days 0.0636 hours 3.786376e-4 weeks 8.71345e-5 months .

l 7/9/83' The Reactor was critical at 1655 hours0.0192 days 0.46 hours 0.00274 weeks 6.297275e-4 months .

l The Turbine / Generator was-rolled at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months and followed with parallel to the system at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months .

'7/10/83 Power was-increased to 69% by 0858 hours0.00993 days 0.238 hours 0.00142 weeks 3.26469e-4 months and held at this point due to low system demand.

,7/11/83 The Unit was loaded to 100% power over a 5-1/3 hour ramp.

l' The AB Emergency Diesel Generator was inoperable for a 5-2/3 hour-period while an air valve was replaced on the j

rack trip cylinder.

Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

R.

S. Lease Telephone:

(616) 465-5901 Date:

8/5/83 Page:

2 of 3 7/13/83 Unit power was reduced to 95% to place the Reheater Steam Coils in service and then returned to 100%.

Total time below 100% was Sh hours.

7/14/83 The Reheater System Coils were removed from service at 1538 hours0.0178 days 0.427 hours 0.00254 weeks 5.85209e-4 months .

Unit power was reduced to 95% with the intent to return six of the eight Reheater Steam Coils to service.

The interlocks on the two Reheater Steam Coils that were to remain out of service had not been properly bypassed.

The Unit power was returned to 100% without any Reheater Coils in service.

Total time below 100% was 4h hours.

7/15/83 Power was again reduced to 95% to return the six Reheater Steam Coils to service.

This was delayed due to a malfunctioning Coil Steam Inlet Valve, however the power was returned to 100% with the six Reheater Coils in service after 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

7/16/83 The Steam Supply to the six operating Reheater Steam Coils automatically isolated at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months due to a high coil drain tank level.

Unit power was reduced to 95% to place the six Reheater Steam Coils in service.

Total time below 100% was 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

7/23/83 Unit power was reduced to 98% for testing of turbine valves.

During the testing the "B" set of stop and control valves operated in reverse sequence.

Proper sequence is for the control valve to close first to be followed by the stop valve.

The control valve limit switch and associated relay were exercised.

The valve retested satisfactorily.

Total time below 100% was 10k hours.

7/27/83 The Offsite Emergency Power Source was out of service for a h hour period while an Offsite Circuit was test energized.

7/28/83 The North Half of "B" Condenser was out of service for a 9

hour period for checking of tube leaks.

7/30/83 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 North Half of "A" Condenser was out of service for a 16 hour1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months period for checking of tube leaks.

7/31/83 Unit power was reduced to 30% over a 6h hour ramp for repair to a steam leak on a turbine valve leakoff line.

Reload of the Unit was initiated at 1625 hours0.0188 days 0.451 hours 0.00269 weeks 6.183125e-4 months .

Unit load was held at 48% power starting at 2028 hours0.0235 days 0.563 hours 0.00335 weeks 7.71654e-4 months due to an indicated Quadrant Power Tilt.

Unit loading was again initiated at 2150

Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

R.

S. Lease Telephone:

(616) 465-5901 Date:

8/5/83 Page:

3 of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Unit power was 65% at the close of the reporting period and 100% was reached at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months on August 1, 1983.

The Control Room Cable Vault "Halon" Fire Suppression System remained inoperable the entire reporting period.

This system is being evaluated for required modifications.

The backup CO System remains operable.

2

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 8-12-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1983 M-1 The #4 reactor coolant pump controlled leakage seals required frequent make-up water to maintain the level in the standpipe.

Inspected the #2 and #3 seals. Replaced the #3 seal ring and runner and the #2 seal ring.

M-2

2 steam generator stop valve dump valve, MRV-221, was leaking by.

Replaced the valve seat ring, stem, disc pin and gaskets.

Had the valve tested.

H-3 The #2 steam generator blowdown system containment isolation valve, DCR-320, failed due to separation of the valve stem and the air operator stem. Replaced the valve stem, stem pin and gasket. Also, repacked the valve and had it tested.

C&I-l Reactor coolant system loop 2 wide-range cold leg resistance-temperature detector, NTR-220, which open-circuited 13 April 1983, was replaced with a new one, S/N N60098. The corresponding elec-tronics signal processing modules and chart recorder were recal-ibrated.

C&I-2 Steam generator #2, channel #1, steam flow indicator MFC-121, read 500,000 lb/ hour when flow rate was zero. The transmitter was reading 0.6 ma. high and was recalibrated. The system was refilled and valved-in. Correct steam flow readings were verified.

C&I-3 Control rod position indicators were greater than 12 steps ott of synchronism with rod demand. Positions of rods J-3, L-e, N-ll, C-5, C-9, N-7, C-7, N-9, C-11, K-8, and H-6 were determined by performing Instrument Maintenance Procedure.048.

Positions of rods J-3 and L-3 were determined by monitoring the stationary rod gripper coil voltage while the rods were stepping. During troubleshooting, an " urgent failure" alarm was received on shut-down bank D, which required replacement of a fuse. A spurious

" urgent failure" alarm was received on S/D bank C.

C&I-4 Unit vent air particulate and radiogas monitors, R25 and R26, sample flow system and pump were checked over. The pump was re-placed and all loose connectict.s were tightened. Operation of the sample flow system was monitored for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to verify op-eration.

I u

m

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 8-12-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1983 C&I-5 Emergency diesel generator, 2AB, had a control air leak at the fuel rack trip cylinder shuttle valve. The shuttle valve air exhaust device was replaced to correct the air leak.

C&I-6 Refueling water storage tank purification system heater #2 would not operate in the " automatic" mode. Temperature switch ITS-900 circuit had failed due to a shorted transistor. The setpoint was adjusted properly to 145 F and the system was returned to service.

The temperature stayed between 80 F and 100 F.

Technical Specifi-cations were not exceeded.

C&I-7 Control rod, H-8, position indicator deviated greater than 12 steps from rod demand. The rod position determination procedure, IMP.048, was performed. The deviation was verified to be only 6 steps, well within the Technical Specification limit.

C&I-8 Steam generator #4, steam flow instrument channel #2, failed low.

The appropriate bistables were placed in the trip mode within the 1-hour limit. A calibration problem attributed to instrument drift was identified and corrected on the channel #2 square-root extractor. Channel #2 was returned to service and the bistables were placed in "nonnal".

-

ML20024F102

Text

Navigation menu

Search