ML20065T149

Monthly Operating Rept for Aug 1982

ML20065T149
Person / Time
Site:	Cook
Issue date:	09/13/1982
From:	Gillett W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20065T137	List: ML20065T136 ML20065T149
References
NUDOCS 8211020239
Download: ML20065T149 (9)

Text

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DCC*CTNO. 50-315 DATI 9/7/82 COM?LRTIC EY W. T. Gillett TILI?HONI 616-466-5901 c?In !NG 5 ATUS Donald C. Cook 1

No::s

1. Uni: b.a==:

Auoust. loRP

2. Reportis;?sriod:

3250

3. Lkensed The. :1 Power (MW:):

1089

4. N =epInt: R.uin;(Cross Liwe):

1054

5. Desi:n E===i=1 R::in;(Nec MWe):

1080

6. 5b dmu:e Depend.ble Capacirf (Cron MWe):

1044 T. M=d--

Dep.d:h!: C::::i:f (Nes MWe):

S. If Ch:=;es 0 =r in Capaci.y R::i=;s (1:=s Nu:nE=r 3 Threu;h 7) Sine: I. st Repor:. Give R:= orts:

+

9. Power L:ve! To Which R=s:6-- d.If Any (N=: Mwe):

10. Re: sons For R==i:: ices.lf A=y:

This Month Y.-to-Cate.

Cu=uh:ive 744 5831 67,199

11. Hou:s != R:por:in; P:: icd

12. Number Cf Hou:: R==::t W:s Cri:i=1 49.606.5 0

3333.3 0

0 463

13. Re:c:or Reserve Shu:down Hou::

0 3301.6 48.523.8

14. Hour: Cen =::: Cn.L1==

0 0

321

(

15. Uni R: serve Sh=tdown Ho==

0 10.505.062 140.868.251

16. Gross The:=:1 I=::;y Cen =::d DiWE) 0 3.453.420 46,335,200

17. Cross Ees:n=1I c ;7 Ge=e=::d G.tWH) 0 3,332,395 44.573.073

13. Ne: Ee==i=1I=: ;y Genen: d p:WE) 0 56.7 72.2

19. Uni: Serri=.::: tor 0

56.7 72.2

20. Uni: Amih' i!I:y :=:or e

0 54.7 67.3

21. Uni: C:paci:y 7:::=r (Usin; MDC Ne:)

0 54.2 64.0

22. Unit Caa: city.::::or (Usin: DIR Ne:)

0 24.8 8.3

23. Uni: For::d Cu::;e R::e

24. Shutdowr.s Scheduled Over Nex: 5.\\ ton:hs (Type. D:te.: d Du ::fon ofI:ch1:

25. If Shu: Down A: Ind Of Repor: Period. Isti==:ed D:ce of Star:ue:

. 25. Units In Tes: S::: s (Prior to C==er:in! Oper:: font:

Fore =st Acrieved 1

INITIAL CRIT:CALITY INITIA L I'.ICTR:C;W CC.*.i..:I?.C:A :. 0?ET.A T:0 N i

tut 71 8211020239 820913 PDR ADOCK 05000315 R

PDR

F AVERAGE DALLY UN!T POWER LEVEL DOCKET NO. 50-315

(

UNIT 1

OATE 9-1-82 COMPLETED BY A. Might TELEPHONE 616-465-5901 MONTH Auaust DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

(

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

25 0

11 0

27 0

12 0

28 0

l i

13

_L,,__,,,____

29 0

l 14 0

30 0

(

l 15 0

31 0

l 16 0

L INSTRUCTICNS On this fonnat list the average daily unit power level in MWe-Net for each day in the reporting month.

Comoute to the nearest whole megawatt.

I

a S

I L N UNIISiltilDOWNS AND POWtilt itEDirilONS DC Cook - Unit 1 k

Dr ili 9-13-82 August' 1982 COntPl.EXEb DY B.A. Svensson 616-465-590T-Iti Pult'l AIONIll 1El.LI'llONE n.

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LC 8ihC i8W 088CLitvC e **

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-ji g jsy livens uy

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Atis.ui io No.

Date y,

t itepius #

6/O EU Psevens Itecussenic 5 ;f3 e'

c U

g e

Q 185 820703 S

744 B&C 1

N.A.

ZZ ZZZZZZ The Unit was removed from service at 0146 hours0.00169 days <br />0.0406 hours <br />2.414021e-4 weeks <br />5.5553e-5 months <br /> on 820703 for scheduled Cont'd.

Cycle VI - VII refueling and main-tenance outage. The Unit remained out of service the entire month.

I 2

3 4

ID l'oeccil iteason:

kicihoil:

Eminini (; Instinisinen S. Stheilnical A l Inspmes.1 ailme (Laplain) l l.lannal los Picpaiation ut Data 11 kl.iinicnance or Test 2-klannal Sesam.

lini:y Sheels lui 1.i.ensee

(' ItcInchug I Aninmainc & sam.

I vens Itepin e il l'Iti I ale INiliti (;-

D llegulaimy Itestiscii ui

-l Oihes liixplaml 0161l 1 Opcsalos l'saining & litcsise 1 xaminaison 1: Ailuunissiative 5

INinin I. S.une Soince G Opes.iiinnal I nos Ilixplain)

P8/ / /)

ll ushes (lisplain t

+

UNIT SHUTDowSS AND POWER REDUCTIONS INSTRUCTIONS Th:s report snould desen:e 211 piant shutdowns dunng me m a::rsance Alth the ts:le secear=g on de report form.

report penod. In addit:on. tt saould be the sour:: oiexplan.

If;2tegory a must be used. suppiy bnei::m nents.

stion of up:fi:2nt dips :n average power leve!s. E2:n up2

1:2nt reduenon a power tevel (greater dan M reduct;on LICENSEE EVENT REPORT = Reference the appl =:ie a avers:e daily ;ower tevei for tne pre: ding ;4 hnunJ reponscie :cunence ;erumm; to de outage or ; owe.

remnen. Enter de dnt four ;2ns tesent year. sequenn2.

could be noted, esen though te urut may not have ~:een snut down completely. For suen reducuens a power evet.

repcrt number o::unence ; ode 2nd re: ort type) of me 0,ve l

tne duration should be listec as zero, the medod citedr.ncn pin desipanon as des:nbec m item 1. 3: Inst wtons :;r inculd be listed as 4 (Other) 2nd the Cause and Corre: ve Prenrauen af Data Entry Sheets for L::ense Event Repen Acuen to Prevent Re:unence alumn should exp!am. The (LER) FU (NURIC-0161). This mformat:en may not be Cause sad Corte:nve Acnon to Prevent Re urren: column

= mediately evident for cl! such dutdowns, of :ourse, s:nce should be used to provide any needed explananon to fully furtner.nvestgsuon may be requ: red to ascertam whetner or desence the ::rcumstances of tne outage er power reduction, not a reportsole oc:urrence was mvolved.) If the outage or power reducton will not result in 2 reportsele oc:urren:e.

NUMBER. T5s :clumn should indinte the sequent:21nu=.

the pounve mdi:stion of mas !sck of eort:12t:en should :e ber assiped to each shutdown oc ugmScant reduct:on m power noted as not 2ppliable GA).

for that alendar year. When 2 shutdown or s:gmdcant power SYSTEM CODE. The, system in wru:n the outage or pcwer reduenon begms m one report pened and ends m snother.

an entry should be made tot both report penods to be sure my the two d: git ecce et.

reduenon or:g:nsted m.ould be noted.

.1 snutdowns or stptd:2nt power reduenons are reported.

cmit G. kst=nens mr heparsnon p Dats ennysnens n

for Licensee Event Resort (LER) ru,e GLREG4161).

unt:12 unit u..as 2:u.:eved its..rst power generation no num.

ber sncuid be assiped to es:n entry.

Systems that do not nt any existmg =de should :e denp2 ted XX. The : ode ZZ should be used for those events wnere DATE. This column should =dicate de date of the start 2 system is not appil: sole.

of each shutdown or upinant power reduccon. Repcrt as year. mcnth. and 223 August 14.19M would be reported COMPONENT CODE. Sele:t the most apptcpna:e.omponent is 77CS14 When a shutdown or up:Sant power reduen:n f om Exhibit !. Instru:nons for Preparzuen of Data Entr) beg:as m ene report pened 2nd ends a r.nother,2n entry should Sheets for Licensee Event Report (LER) Fde (NUREG.0161),

be made Mr botn report pencds to be sure 211 shutdowns usmg the folicwmg :rtuens:

or up S:22 : power reductions are reported.

TYPE. Lse "F" or "S" to indicate either "For:ed" or " Sche.

duisd." respeenvely, for each shutdown er signid:2nt power B.

If not 2 :omponent fat!ure, use the reisted com=cnent:

recuenon. Fer:ed shutdowns m:!ude those required to be e.g.. wrong valve operated through error: !!st valve as stusted by no Ister than the weekend followmg dis very

omponent.

cf an off. normal condition. It is re:cgni:ed that some judg-ment ts required a utegonamg shutdowns in t!us way. In C.

If 2 casm of fattures occurs. the Erst :cmponent to mai.

general. 2 forced snutdown is one that would not have been function should be listed. The secuence of events.mciud.

cmpleted in de absen:e of the =ndition for which ectreenve ing the other components which i~2il. shoulet be des nbed acnon was taken.

under the Cause sad Corre:nve Acuen to Prevent Re:ur.

rence column.

DURATION. Selfaxplanatory. When a shutdown extends C mp nents that do not At any ex:stmg ::de snould.se de.

beyond the end ci 2 report penod. count only the t:me to the signated XXXXXX. The code 777777 should be used for end or. de recort pened and pich up the ensumg down time events where 2 component desapanon :s not appiin:le.

m me foi!cwmg repcrt peneds. Report duranen of outages ruunded to the nearest tenth of an hour to (20:litate summanen.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

ine sum of the total outage hours ;ius the hours the geners.

REN r U

• • N"I#'

tor was on line snould equal the gress hours a the report:.g explain de ::rcumstances of the snutdown or power recuenen.

pen d.

The column should mcfude the spe::nc utse for each snut.

down or upancant power reduenen and the immediate anc REASON. Catepnze 5s :etter designanon m accordan:e "I """ ** ""U" ** U '"

• N '"' '

• EE ' E "'

witn the taoie 2 pearmg on the report form. If :stegory 1!

ate. Th:s ciumn snould also :e used for 2 desengt:en or tne must 5e used, su:pp b :Ji comments.

maior safety related cfreenve mamtenance performed dunna the outage or ;cwer reduenon m:!ucmg an identin:2nen of METHOD OF SHUTTING DOWN THE REACTCR OR REDUCING POWER. Catepnee ev numeer desensuun

• • #""'21 p2m 2enty and a upon of any smgie re! esse (

radiosetmty or smgie radiation ex:csure spect042ily 21sec:.

I%:e that this difrers from the Edison Electri: Insutute 4ted *"h the out:re whzen seecunts for more taan 10 per;ent tEEli defmnions et "Ferced P2ntal Outsas" and "Sene.

ol de 21!o*2oie 2rnual v2iues.

uied P2ntal Ourap ' For these tenna. eel uses a shange ot For long textual re:ons eentmue narranve on se:2rste ps:er

.M MW as the breai point. For larger power resetors.30 MW

.nd reteren. the shutdown or power recu.::on tu m

s t..o small a.nange to wanant npianation.

narranve.

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j Docket No:

50-315 Unit Name:

D. C. Cook Unit 1 Completed by:

D. R. Campbell Telephone:

(616)465-5901 Date: 9/8/82 Page:

1 of 1 MONTHLY OPERATING ACTIVITIES - AUGUST 1982 Highlights:

The Unit entered the reporting period in Mode 6 to continue the refueling outage that was started July 2, 1982. The entire core was unloaded to permit work on IM0-128 (Letdown isolation valve from the Reactor Coolant System to the Residaul Heat Removal Systems.), which required draining of the RCS loops.

Repairs were made to IM0-128, the loops were refilled and core reload started. The Unit went into Mode 5 at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, August 30, and remains in this Mode at the present time.

There was no electrical generation for the month.

Summary:

8/9/82 Reactor core complete.ly unloaded from the vessel and the Reactor Coolant loors drained.

8/16/82 Unit back to Mode 6 and core reloading started.

8/20/82 Core loading completed.

8/23/82 Reactor head replaced.

8/30/82 Unit in Mode 5.

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 9-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-670T PAGE 1 of 4 MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1982 M-1 Plugged ten tubes in steam generator #12 and ten tubes in steam gen-erator #13. The tubes were plugged as a preventive measure and are those adjacent to the tube lane blocking devices.

(Row 1, Columns 1, 2, 3, 4, 5, 90, 91, 92, 93 and 94.)

M-2 AB Diesel aftercoolers ESW regulating valve, WRV-721, was sticking partially open. Disassembled the valve, replaced a broken 0-ring and bonnet gasket. Had valve tested.

M-3 Component cooling water containment isolation check valve, CCW-135, failed to meet type C leak rate test criteria. Lapped the valve discs and replaced rubber seats. Had the valve retested.

M-4 The fuel transfer system was damaged during dry checkout prior to re-fuel ing. Repaired the transfer cart, upender, upender basket and tracks.

M-5 No. 4 steam generator blowdown regulating valve, DRV-342, had a body-to-bonnet leak. Replaced the valve seat and plug gaskets. Replaced the operator diaphragm and repacked the valve. Had the valve tested.

M-6 A leak was discovered in a socket weld of the 1" vent line on the East RHR Heat Exchanger upstream of the vent valve, RH-125E. Re-welded the joint and had necessary NDE performed.

M-7 Inspected the controlled leakage seals on #11 reactor coolant pump.

Replaced #1 seal insert, ring and runner, #2 seal insert and ring, and

1. 3 seal runner.

M-8 Upon disassembly of the West Centrifugal Charging Pump, visual inspec-tion revealed erosion of the internal cladding in the area of the dis-charge nozzle. The indications were ground out and welded. NDE was completed.

M-9 Pressurizer power-operated relief valve, NRV-153, leaked by. Replaced valve internals and gaskets, repacked valve and had it tested.

M-10 Inspection of IM0-128, the motor-operated isolation valve for RHR pump suction revealed a broken valve disc holder. The valve stem, valve discs, valve disc holder, frame, bonnet studs and nuts and bonnet gasket were replaced. Repacked the valve, reset valve travel limits and tested.

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit Nc. 1 DATE 9-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 4 MAJOR SAFETY-RELATED MAIN 7ENANCE AUGUST, 1982 M-11 A leak developed in the instrument line to the West RHR system flow instrument IFI-331. Ground out socket weld and rewelded. Had re-quired NDE performed.

M-12 The North waste gas compressor was not operating properly. The dia-phragm for the suction valve, RRV-378, was replaced and the valve was tested satisfactorily.

H-13 A leak developed in the drain line for the East RHR heat exchanger.

Ground out socket weld and rewelded. Had required NDE performed.

M-14 CVCS letdown regulating valve, QRV-160, had a body-to-bonnet leak.

Replaced the valve gaskets and bonnet studs. Had the valve tested.

M-15 A leak developed in the equalizing line for the RHR valve, IM0-350, on the West RHR train. A cracked weld was grounded out and re-welded. Necessary NDE was performed.

M-16 The nitrogen containment isolation check valve to the reactor coolant drain tank, N-160, failed to meet the type C leak rate test criteria.

Opined valve and cleaned internals. Valve tested satisfactorily.

H-17 The CTS pumps suction valves, IM0-215 and IM0-225, were leaking by.

Lapped the valve discs and seats and repacked both valves.

Had valves tested.

M-18 The charging pump suction valve from the RWST, IM0-910, had a body-to-bonnet leak. Replaced the bonnet gasket and bonnet studs and nuts.

Had valve tested.

M-19 Two short sections of the containment divider barrier seal were found to have surface cracks. Replaced cracked sections of seal material.

M-20 The RHR letdown regulating valve to the CVCS system, IRV-300, had a body-to-bonnet leak. Replaced the bonnet gasket and had the valve tested.

M-21 A leak developed in the equalizing line for the RHR pump suction valve, IM0-350. A 3/4" pipe and elbow were replaced. The required NDE was performed.

M-22 An oil leak was observed on LAB emergency diesel #4 front cylinder inlet valve pushrod sleeve. Replaced the gasket and 0-ring. Had the engine run for test.

.~

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 9-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-590T PAGE 3 of 4 MAJOR SAFETY-RELATED MAINTENANCE ~

AUGUST,1982 C&I-1 AB diesel generator starting air receiver pressure low, annunciator panel 19 drop 3, was not received with the pressure at 160 psig. Re-pair of a broken wire on a terminal board in the diesel room corrected the annunciator problem.

C&I-2 "E" motor driven auxiliary feedwater pump blackout sequence timer was found to exceed technical specification maximum time. When connected to a relay tester, the time relay " double pumped". Tightening the prime contact mover on the time relay corrected the trouble.

C&I-3 Containment auxiliary subpanel annunciator panel #24 experienced 'a loss of 250VDC power during the performance of a containment sump flow capacity test. Troubleshooting the AFC-2 circuit revealed an error in wiring at the containment 650' level airlock. This error had caused four 250 VDC power supplies plus an annunciator flasher card to fail. Replacement of the defective components restored power to the annunciator panel.

C&I-4 Radioactive liquid release flowrate gauge RFI-285 was indicating 18 gpm flow with no actual flow through the piping. This gauge is used to document radioactive liquid release. The flow D/P transmitter, squareroot extractor and flow indicator were recalibrated to specifi-cations, to restore correct flow readings to RFI-285.

C&I-5 Fuel manipulator crane " tube down" indicator was inoperative. The actuating proximity switch was replaced to correct the " tube down" indication.

C&I-6 During testing of l AB diesel generator, the mechanical overspeed t f p device did not trip the engine when its setpoint was exceeded, although proper mechanical operation of the device was observed. The failure to trip was ultimately caused by failure of the governor power inverter due to blowing of a fuse. With loss of power, the electronic over-speed relay, Dynalco speed sensor, and Woodward mechanical governor were all inoperative.

"AB" battery was still powering trip solenoid valve SV-5, however, the operator was able to trip the engine by de-energizing SV-5, allowing release of the control signal.

C&I-7 Low suction pressure trip annunciator was received on the "W" motor-driven auxiliary feedwater pump. Replacement of a sluggish-acting Mercoid pressure switch corrected the difficulty.

, '. ~

DOCKET N0.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 9-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 4 of 4 MAJOR SAFETY-RELATED MAINTENANCE AUGUST,1982 C&I-3 Accumulator #4, narrow range pressure channel IPA-141, failed low and then returned to a normal pressure reading. Defective contain-ment penetration connections were reworked and the pressure trans-mitter was recalibrated to insure reliability and accuracy of IPA-141.

C&I-9 Nitrogen supply valve to accumulator, GRV-313, was leaking N2 to at-mosphere. A broken diaphragm assembly was replaced and missing screws on the regulator gauges were installed to repair the N2 leaks.

l