ML20006G124

Monthly Operating Repts for Jan 1990 for LaSalle County Nuclear Power Station Units 1 & 2.W/900210 Ltr

ML20006G124
Person / Time
Site:	LaSalle
Issue date:	01/31/1990
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9003050102
Download: ML20006G124 (22)

Text

86/26/mi 31151 NO.083 P002 ,

i )

-e .

'o..

' ' f, ,

- 0: _ ...:.._ :f. Editen 1 Lale le County Nucleer 3 stion {

RUW butee1. Sea 240  !

MeteNIles,Ithnet$1341 l ' Teleghone 416/38F 6761

)

i Februsty 10, 1990 I

l f

Direct.or of Nucloor Reactor Regulation  !

United States Nuclear Regulatory Copelaston >

Mail!StationP1- L37 Weehlngton, D.C. 20555 ,

I A'!"IN : Document :entrol Desk i Gent.'leme n t Enclosed for your information la the monthly performance report covering j LaSalla County Nuclear Power Station for January, 1990. t i

Very truly yours, e.

l. j

0. J. Diederich 1 f hgStationNapager l Lass 11e County Station i

l- GJDIJWT/psk i.

F.ncIosute set) A. D. Day (0, NRC, Region I!!

I NRC Resideat Inspector LaSalle  ;

111. Dept. of Nucient Safety l

e P. Shemnus ti. NRR Project Manager '

l D. P. Oslla, Ceco

' , D. L. rarr ar, Ceco l

2NPO Recor $s Center L. J. Anas tasia, AIP Coordinator, Nuclear Services J. E. Kuskey, GE Resident T. 1. Kovech, Manager of Nuc1 ear Licensing ,

W. F. Naughton, Nuclear fuel Services Hansger ~

C. F. Dillon, Senior rinancial Coordluatur, LaSalle .

Terry Novotney, INPO Coordinator, LaSalle Station T.A.Hmperich, Regulatory Assurance Supervisor i J. W. Glaselter, Technical Staff Supervisor r

Cent,41 ri se

[l iS818a8!388agi.,3 znD15 e im De '\ .

. - , + - - ~ , - ~ -_

E W/26ti: 31:51- C'd.LRJ O ,

4 -

c:* ..

4 LasALLE MUCLEAR POWrit STATICII UNIT 1 MONTHLY PERFolethWCE REPORT .

JANUARY 1990 C00440NNEALTH EDISON COMPANY m-MRC DOCKET HO. 0$0-373 LICBMSE NO. NPT-11 l

e ECADTS/5

.m.. -

-. . ,_,....,,,s._-- . . . - - . . . _ . - - ,__ . _ _ _ _ _ _ - _ _ . _ . _ _ _ - . -

86/26/d 31:01 to.013 P004 '

l

. , - .  ;

I TABLS OF CONTENTS I 1

1. INTRODUCTIGl

11. REPORT .

A. $1#06 arf 0F OPERATING EXPERIENC8

PLANT 3R PROCEDURE CKANGts, TESTS, RKPERIMENTS, AND 5&FETT RELATED '

B.  !

NAINTE RANCE

1. A mendments to Facility License or Technical Specifications

2. C hanges to procedures which are described in the safety ,

A nalysis Report l 3, 1 ests sad Esperiments not covered in the Befety Analysis Report orrective Maintenance of Safety-Related Equipment

4. C

5. C ompleted safety Related Modifications I

C. LICEMi>Et EVENT REPORTS +

D. DATA MADULATIONS

1. t yerating Data Report

2. average Daily Unit Power Level '

,,, 1. Unit Shutdowns and Power Reductions 1 F. . UN100 5 REPORTING REQUIREMENTS

1. i dain Steam polief Valve Operations ,

2. ECCS System Outages

3. Off Site Dose Calculation Manus! Changes

4. dajor Changes to Radioactive Weste Treatment System

5. Indications of railed Fuel Elements l

)

r EC ADTS/ 5

^ ^ ^ -^ - .- . - . - _ _ _ _ _ __

l t

I 4

i

1. INTRODUCTIGI The LaSalle hCounty Nuclear Power Station is a two. unit facility ownedEach Edison Company and located near Marseilles, Illinois.

by Commonwoolt unit is a a sillag Weste Water tooetor with a designed met electrical output of heat je rejected to a maa-ande coe11ag pond uslag 1076 Negawatts. The architect-engineer was the Illinoi sLundy River for make-up and blowdows.

and the primary construction contractor was Sargent and Comonwealth Edison Company.

17, 1962.

Unit One wa s issued operating license number NPr-11 on April Initial criticality was achieved on June 21, 1982 and comercial power operation vos comenced on January 1,1984.

This report was comp!!ad by John W. Thunstedt, telephone number ,

(815)157 61 61, entension 2463. e P

F r .

1 P

3CADT5/$

86/26 4 : 3?. 52 10.013 P006 3 . e

!I. MCIIT1tLY RSM*T A. SUDe4ARO OF OPERATING EKFSRIEllCE I

Dag 1h E_vant

1 0 >00 Reacter suberitical, generator off-lise, L1803 in progress.

l 4 3 326 Reacter critical 7 3215 Reactor shutdows, unable to synchronise generator.

9 0045 Reactor critical l 10 1012 Generator on-line 1 200 Increased power to 819 MWT 12 1 417 Generator trip for Turbine Trip testing 1 452 Generator on-line i 13 ll100 Increased power to 2501 MWT 16 0200 Reduced power to 1802 MWT for control' rod alignment LOOO Increased power to 2900 MWT ,

1. 16 2230 Reduced load to 2761 MWT for CRD maintenance 19 2100 Increased power to 2862 MWT 1430 Increased power to 3070 MWT 20 1700 Increased power to 3300 MWT 23 0000 Reduced power to 2880 MWT for CRD esercising ,

1100 Increased power to 3320 MWT 25 0300 Reduced load to 2690 MWT for System load 1100 Increased power to 3290 MWT 26 0300 Reduced load to 2947 MwT for System load I' 0700 Returned to full power 27 28 0200 Reduced power to $10 MWE for control rod alignment 1800 Returned to full power 29 0100 Reduced power to 850 MWE for System Load Returned to full power f- 1200 i

2CADTS/5

,r--- ., ,~v- -

.. . . _ - . . - . . _ . - . . = . . _ . _ - _ . _ - _ . .

bC.013 . .Pos? _

9 gar MRe E**** -

1

• 0000 Reduced power to 993 Nws for CRD esereleing 30 1100 Returned to full power  ;

34 00 teactor critical, generator on-line et 1130 Mw8.

31 R PROCEDURE CHAlt058, T8875, EEP8RIMENTS AND SAFETt StLATED j

9. PLANT O NA!NTallANCE.

1. M ienements to the Facility License or Technical specificaties.

D avision to the Pressure / Temperature curve referenced in T9chnical Specification 1/4.4.6.

2. C 4anges to procedures which sto described in the Safety l Analysis Report. l L LP-89-012 " Unit 1 Operation with RPV Flange Seal Leak" i

This procedure provides the instructions necessary to ensure that proper controls exist en the status of the Unit 1 Reactor Pressure Vessel hood f asage seal leak detector switch when the inner head seal 0-ring is leaking. l L

LP-90-002 " Bypassing of Unit 1'R$C8 for Scram Insertion Time 1 esting"

1. ~' This procedure provides the methode and controls to allow bypassing the Unit 1 Rod Sequence Control System during ,

control rod scram testing above 20% power.

3. Vests and Emperiments not described in the $sfety Analysis r toport. '

None)

4. 4ajor corrective maintenance to Safety-Related Equipment.

(see Table 1)

5. :ompleted Safety-Belated Modifications.

(See Table 2) v 2CADTS/5

. ~.

O.4- Tama 1 -

3 .-

, g s

muon conneenet NarmEsamer to . t SArETT-RELATED SQU1FDENT

• • sm-ts amo crrscTs ConseCTITE acTIm g woan meoutsr .ON SAFE PLANT OPERATIm e.

i CAUSE OF MALFUNCTION --

NUseER Cose'ONENT E

4 i in-st 0) (geone) l (Galt 1) Beplaced switch

~Bigh Pressure" alarm 0 D/G Crankcase Internal failure activated L95251 pressere switch toplaced seal Door f ailed ILET Encessive wear l L96024 Forsoneel access ~

l' hatch immer door seal Depleeed seal l Door failed I4ET l Persommel access Excessive wear L96557 hatch outer door hanemheel shaft seal ZCADTS/5

i l

.. , i j

.  ! i

tC.013 P009 06/86/4: 31:52 s.l TAsLE 1 l courtg7so skrsvr-a:LArso woorricAttons  !

i

. s

=.. a _sesentestou  ;

N01 0-se-001 1s s et,i tallaties of a pasonry wall steel support columa, i 71 0 and in intended to provide 1steral sopport for Seismic ,

Co togory :t masonry wall panel.

M01 1-87-008 In stallation of a " Local-Remote" transfer evitch and a new s control circuit fuses to esisting switchgear brooker ,

on "0" CNP OD001P Feed Brothers.

co ntrols for the D/0 l l

M01 1-87-011 1 stallation of a local-Romote" control circuit fuses to esisting switchgear brooker transfer switch and a new s l

of c> ntrols for ESS Division 1 Feed trookers.

N01-1-87-014 I nstallation of a " Local-Remote" transfer switch and a new e

t control circuit fuses to esisting switchgear brenner .

c ontrols for D/G "0" Teod Breakers.

M01 1-87-028 I nstallation of " kill pushbuttons" and rearrangement of r

ecorders and recorder pens for the 1N13-P602 panel in ,

a ccordance with Human Factors.

s pilt annutciator lato two esparate alarm windows for the high M01-1-87-029  :

o o

nd low pressure alarms to allow Control Room O  !

panel in accordance with Human Factors.  !

I hearrangement of the Vent and Purge damperi hcontrols Humma located on M01-1-87-030 ,PM06J into a logical configuration in accordance w t

" actors. )

bypass valve f

M01-1-87-033 [nstallation of an alarm to indicate that turbine is open located on 1PM02J panel in accordance with Ruman l rectors.

Out and cap downstream of the double block valves in the M01-1-87-092 Reactor Recirculation Low Point Drains. t rial Fill drywell penetrations M-23 and M 24 with shleiding ma e M01-1 87 094 to reduce neutron and gamma radiation streaming at reactor building elevation 766'-6.

M01-1-88-004 pep acing the existing 125 Volt, Division 1 b l

for the bettery and it's associated charger.

h Installation of two (2) start permissive white lights for eac M01-1 88-030 Reactor Recirculation Pump on Panel 1H13-P602.

/B valves, Replace the double #1eribleconfiguration, wedge disc. for the 1933-F067AThe existing M01-1-89-001 ~~'- *a." ^a disc to be

p .....................................e.......... - - - - -. . - .- ~ ~ _.- .

c,,

. '

t FC.013 P012 06/26/4: 31:52 ECADTS/S 90Catt W . 99 H 73 pit 1,gggi,g W t 6:

2 2 : : = ni r2; p,t ap atis M1A stegaf MitFebrestr 14,1999 '

g, C0lrLffD ST J.W. 11458159f 7tLIPIGE (MS) NY-6761

"' l

. . . . . GR088 80881R 8EPW11# PERl#3 JANutRYi 996 -

. etPOR115 Ptt!N: I.636

'3,323 Ilu KPOS CAPACITY (Itir-teth 1,070

?

Wt).

1. t WREWTLY AUTHOL120 POW t Ltytt (I 9(llGN EL(CTRICAL LAf14 (Itir-Wil .

(NOM)

' MT) 'Mt*Nel1 -  :

3. P0dtt Ltvtl 10 WICH R($fA!Cf(D (! ,

WM REP 9 tile Ptt!00 MTA 4, 8(4$0N$ FOR Rt51titilDN (if ANY) ,

ase aa ,- y. ., ..

m .,i,.

617.9 32.752.4 6t7.9 .

5. 11 3 t(AC10e Ctl11tAL iHOUps) 9.641.2 4.6 0.4

4. TIM ( REACf0R RtEtyt SNUTDOW (H0 mt) '

517.2 31.935.1 51% >

7. 1191( &(N[AAf0R ON Lid (M0045) 6.4 1.0 4.6 0VR$)

- 4. 114 stNt94YOR 4(SCRV( With0* I f 09.245.162

f. t,4tt,594 1.411.594 e

.WRML (Nt96Y 6tdR4fil (PWt Gf est i 474.572 29.543,l13 474.572 Cross) (

it, (LECft! CAL EN(R&T G(NttniD (MM ft.1M,257 456,?55 456.555 ti. (ttt1R;tAL EMPLY GEN (RA1(0 (m wt) 83.f 61.4 83.1

12. AtACTOR $tiv!CE FAC108 (1) 83.1 64.4 83.6

n. aucw. ...s ue s ,, . .r e ...

59.8 69.5 H.5

14. Stev!CE FACTOR di et.e ..

- 15. ave!LillLITY fat'109 (1) 59.2 51.6 5f.2 16.' Caf 4 CITY FACTOR 'USING MDC) (1) 49.0 56.9 $6.9

17. CAPAt11Y N.10R (U$!NG D($1GN Mfe) (2) 16.4 it.i 14.4

19. FORCO OUTAct FACfot 1: . ...... ........... . ................

19. $Wu1MWS (Nonel SCHEDULCD DVER THC ht(i f wlWS (7 tit. Nit. AND DURM10m P100, ESilmnitD (4fC Or ifARiuh f IF SPJ1MW AI (Nb (N/A) 0F PElORT H

. 3:

s-D.3 tNrIT SEUTDOISBS AND PGIkB EEDUCTICE85 > 20%

e; u.

8j NN i

SETTING DOIA8 TYPE T E REACTOR DE COMSCTITE l TEARLY " *"rus *_---

r a ruun , isinn.un, n--

SEQUE3rrIAL (HOURS) REASON __ ,

l DATE S: SneumOLED NEBSEE 4

Befueling Outage (L1383) 1 278.3 C 9/15/09 5

. 1 4

Unable to synchroeles 60 B generators sketdeus reacter 2 7 F d

during menetenesce ce ,

I generator esciter Turbies trip testieg a 5 ,

5 0 3 12  !

s system lees ,

o a a 2s s ,

5 system lees ,

o a  ;

i s 2, s i 6! .

I a:

i I r

_ _ _ _ _ - _ - _ _ _ _ ., . .. . . . - - . -- ._..____ _ - -_________ _ __________-_-_-_ - ~

J M/26 '0 31 52 8 019 D19 ~ ,

L Jt i <

. 4;,;; iu ,,;

i

• . IEET C. Stem tillt LagaLLI N EftFebrserrit,1990 3.2 utan k!LT wit Podrt ttVE telt-*t) C0lptt10 pf J.W. Titgefut g fittMEW (Ottb514761 l

l l

- alp 0kT Ptt!0tt JugueAT 1996 i i

WT P0lta l pt PMt .... . . ......

....... ......... 1 11 952 t +14 18 943 2 *t( i 19 974 t 3 it 20 1.63) 4

• in t

21 1.076 i 5 11 ,

I 22 1.0ft .

6 it 23 1,476 r 7 *tt

• ' 24 1.ite 8 4 25 t,953 f *6  ;

f 4 26 1,994 il 3

27 1.076 11 22 20 . 962 12 1'3 29 1.026 13 l4 30 1.619 la '99 31 1,042 15 74 ,

l

-- ~n--,

I 96/26e43 31:53 N3.013 P016 p

c e.

i LASALLE NUCLEAR POWER STATIC 31 UNIT 2 MONTHLY PERF03e4ANC8 REPost JANUARY, 1990 F

C00440NWEALTH EDISCal CCNFANT NRC DOCKET NO. 060-314 LICENSE NO. NPF-18

)-

e ZCADTS/7 i

O r

- M /26 4: 31:53 10.013 e' ~ M16'

1. 1. INTRODUCTICR i d by Each The 1,65a110 k 3dioen company and locatedi nest l output of Marseilles,1  ;

commeswes14 unit is a %1 ling Water Reactor withThea arebitect-engineer designed met was electr caW 1018 Megaw atts. j le River for make-up and blowdown.

the Illino t Lundy and the primarr constructies oestracter was Sargent am Commonwealth Edison company. 16, l b

as issued operating licones number NPr.18 en Decem 10, 1944 and commerc er ail Unit Two w tial criticality was achieved on March 1943. Ini 19, 1984.

f power opes etion van comenced on June l This repoi t was compiled by John W. Thuastedt, telephone number (815)357 h761 extension 2463.

1 l

P ,

w e ZC ADTS/ 7

NO.013 pgg7 .,

, 96/26ed: 31:03 .

i I k .' . ' ,

b

. i TABLE OF COWTENTS l

g. INTpaccCTIC N f

11. REPORT S u m Alt Y OF OttEAT1MO EEPERIENCE A.

OR PROCEDURE CHANGES, T8878, EXPERIMEWFS, AND SAPSTY  !

S. PLANT Nh!NTBNANCE kmendments to racility License or Technical Specifications 1.

2.

Changes to procedures which are described in the Safety Analysis Report. ,

3.

Tests and Esperiments not covered in the Safety Analysis Report. l 4.

Corrective Maintenance of Safety-Related Equipment b

5. Completed Safety Related Modifications  :

C. LICD SEE EVENT REPORTS D. DATA TA5ULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level i

1. ~' 3. Unit Shutdowns and Power Reductions l E. UNIQ JE REPORTING REQUIRENENTS

1. Safety / Relief Valve Operations

2. ECCS System Outoges

3. Off-site Dose Calculation Manual Changes J

4. Major Changes to Radioactive Maste Treatment' System

5. Indications of Failed Fuel Elements l

l 2CADTS/7

PC.213 pelg t 06W4: 32:33 t 1

. j e ; ; g ,, .; ,;,

l

13. se0errWLY 2510R7 A. SUD9&M T Or OFREATimo EEPERIBICE _

m h even g

Reactor criticti, generator en-lies at 3050 tert.

1 9000 1400 Returned to full power f

Reduced power to alle Wrt for CR0 esercising and  !

3 D100 System lead  ;

1400 Returned to full power Reduced load to 2950 Mr! for System lead 4 0200 .

1200 Returned to full power  :

Reduced load to 2910 Murt for CRD esercieing l 10 0000 ,

1300 Returned to full power i 3

Reduced load to 3040 MWT for System lead 14 0230 1500 Returned to full power ,

Reduced load to 2930 MIrf for System load 16 0230 I 1200 Returned to full power f Reduced load to 3100 MfT for surveillances l 2330 1000 Returned to full power 17 Reduced load to 3551 MWT for System load 19 2300 l 0100 Increased power to 3266 MWT 21 Reduced lead to 2990 MNT for System lead 0200 1100 Returned to full power 22 i

Reduced power to 2523 MNT for CBD esercising 24 0300 l

1600 Returned to full power Reduced power to 3020 MWT for flow-control-line j 31 0020 evolustion l

2400 Reactor critics), generator on-line at 3154 MwT 1

I' f L

I l

ZCADTS/7 l

3

, EptatMENTS AND ShrBTW atLhTED )

3 ptJJrt 08 McCSDUtt CRANO38, 73578,  ;

MAINTENANCI . I ents to the Feellity License er Techniss1 Spesifiestles. {

l7 1. ' Ament >

SevisL es to the Temperature Pressure curve reforested in Techniesi ,

Spectlicaties 3/4.4.6 f Chang es to procedures which are described is the Safety haalysis [

'3.

Report. i Lst.g o.cos "Overleed 3rpass Test for 2833-F913 Valve" The p urpose of this specist test is to verify the operability of the overl oad bypese cirevitry for the OCs Minipun Flow sypass to l

Suppi- ession Pool valve 3E33-P013.

f Testo and Esperiments act described la the Safety haalyste Report.

3.

(Hone)

4. Majo r corrective maintenance to safety-Related Equipment.

i (Nost) comp leted safety-Related Modifications.  ;

5.

(See Table 2)  ;'

l l

C. LICENSEE EVENT REPORTS f (None) i D. DATA TAWTLATICMS 1

1. Opera ting Data poport (Attached) 1

2. Avera ge Daily Unit Power Level (Attached) ,

3. Unit Shutdowns and Power Reductions (Attached) r ECADTS/7

W26M: 31:53 HO.013 P021

o. .

3015tf C. F74  ;

p.t iPtantig utA gegRt 1Allt fW t pftF(tettyit,1990 COMPLittl 9Y J .tntlNB191 <

e 7tLtPlet ( $1 57 6741  ;

744 I~GPERAf!E SfetW latet est is $ftfl4 Pelt!W:

84841ARY 19,e

' t,.'stegRtts PERIDP: 1,6M m g ItPts CAP 48 tf Uthanti: t,078 l 3,323 ut): 9tt!$N ELICTilCE. hA115 Utle-lut) i 2r tunatstLY Actiettrit P0Wtt ttytt i

(Notel If MT) (MWt Neth

' 3. POWER Ltytt to WHICH Al$fRICTC$ ( i (N/Al REP SilE PEA! W MTA '

4. 9tA80N$ TOR RtliRICT1DN lli MYl- ... ....... ... .......... .......... ..

/ CUMul.Ativt fHIS IIDWTH YtaA10-Daft  ;

7A4.6 144.0 34.t'I.i 5.114t Rtet104 tR11 tral (HD.lPSI 1,116.9 4.0 9.6 OP11 . .

6. flpt R(ACTOR Pt$tRV! SHUTDOWN H 30,427.4 744.0 144.6

7. 11ME tt @ A16R ON L!ht Otcut$1 0.0 4.0 0.9 tMoutt)

t. ttMt GC@ATOR MStkyt SWTDom 2,411,935.2 06.737,9832 ,

pat?,935.2 r- ;tostl

. I@ MAL E44Y LINERATO mMt- 82$,612 425,4(2 79,275.938 w CresO it. Ett(ikICAL ( @ &T Ct W ATO m 795,995 20,634.4M 795.9 5 .

de heti

11. ELECit! CAL ((4T GtNERATO (di IM 9 iM.4 64.4

12. REAC100 6tRVICE f ACTOR (1) 1M.4 79.3 t60.9

13. ADCt0ft AVA!LA>1LifY f ACTO' m IM,9 1M.4 65.4  ;

14. 5ttV!CE FACIOR 0 ; IM.9 65.6 tM.6

15. AVAILIP!L!ir Tar 10P (t) 193.2 $9.4 103.2 ,

16. teFatift fat 10R (USING MDCI U 99.1 56,1 99.1 t?. CA8 AtlIY F AC10P ml>G )($1t,a nue) (11 16.$

18. FORCD DV14E FACICR (1)

E NEXT 4 MONfMS (fff t, DAit Mb D'J8 AT10N OF EACHh

19. SNU100W S SCHEPUL D tht8 1HE Reht! int i .29437 83-17 96 12 Weg 5 t MPIOD. ($11 Matt 0 DAtt or STARfuP; O 1F 5Huit0W AT END Of ttf 0R (NiA)

06/26<4:- 33353 iC.013 pery

.1 f

r ili  ! !

11 I e i1 e

s-a I'Il '

lEn W M M i ~

3

- I -

1 D. ,

.i 1

g B-a

• 5' 'i O O w O 53 i

T I ,

lc a . . .

N ,  !

A I l ~n

p/ Mci 31:53 CSDJ W: tty c., .

• IOSif C . GB H i4

. Clt LAGGt TW pftForuryit,im

.- 9.2 WEIG hlLY #11 P0ER LER Me Net) CDPd19 pf J,5.11tlNSTG1 TERPISE (9ttl*N7 4?st IIrgetPtt106: AsutRY t M i POWA DAY MY POWR ""~**"***"**

17 t,673 I t ,91' 19 t,000 2

1,98I 19 t,t:0 3

t,02,-'

06 9tl 4 1,Ns 1,0' 2

!! 1.072 5 .

22 t,991 6 t$t 03 1,994 7

1,9to 24 t,423 9

1,8P5

?$

1,985 9 1,(99 e 1 tti 24 to 1,( 40 ,

27 t,994 ,

it t, )t3 1,000 ,

29 12 i. )e4 09 t,096 13 1,H!

19 1,074 14 t 144  :

31 997

' 15 i 988 I

- r

__ l

~ ~ ~ ~ ~

.ggg , . 31i 53 -~ ~~tc 013~ ~~CG10~ ~~^~'  ;

f S. UIllgus strotTINO segutsmserts .

. aet v.1,e op.r. tie..

1. seroty<

PL&lff DSSCBIPTItal -

VALVBS. 50 & TTPS or evanT _

ac1UAT1 Cat CCERD171CRI g hemnean (Neme)

2. ECCS System Outages _

ggapaan >

erstr_= ent stant no.

the yes and unit numbers have been ensnitted from the Outogo Number)

(Notes i 11lmit 0) ,

Replace pressure switch 20 0 D/0 I

IUnit 1)

(Administrative) -

8 B RNR (Admlaistrative)

& RHR 18 Over speed testing RCIC 20 Repisce relay to test CY valve 48 IE51.F059 (RI)  ;

Defeat spurious isolation signals i 54 RCIC Steam riow Line-break detection

(Administrative) 58 1E12.F006 (RH) l Check hold-down screws 1D008CA

$9 "A" Air Compressor

( Inspect strainer i I 15 D/G Cooling 66 l Water (MP)

Lubrication 67 18 D/0  ;

( Calibrate oil filter delta-p slarm RCIC 86 Changes to the Off-Eite Dose Celculation Manual 3.

(None).

)

4.

Major changes to Radioactive Waste Treatment Systems.

(None).

5. Indications of railed fuel Elements.

(None) r \

l \

l-ECADTS/5 l I

i

'^^-~-~u- . _ , , , -""T*"m--m

P bfbJ KSQ&J Qlf4 0

..e- ,,

UutQua AsPtattmo asQUIRausWte

.- s.

1. Safety /Itelief Valve Operatione PLANT DESCRIPT!W Wh',#58 NO & TYPE or aven, _

cearntricas I ggg gggggs acutfAT1 cats l

(Wese) i

, 2. sces Sj etos Outages Mia W e out p1 me. kmynsptT and unit deelysators have been omittee from the Outage Wember.

NOTE: The year Replace costector 5

RNR WS Cooler Fans Replace low air pressure switch 14 28 D/G 28 D/0 Calibrate var meter 18 l 2A D/0 Air Compressor Rohild compressor 24

r 2DC03CA Repair compressor 28 Perform 50 laspection 2E12-F0268 (RM) 31 Perform inspection 35 2E12-F094 (RN)

Perform L85-SQ-112 36 2C12-F094 (RH) g Perform R$ inspectica 2E12-F0268 (RH) 37 2D008CA Inspection 38 Lubricate couplings, cleas coolers 2A RHR SW 41 2A RRR Pump Perform 128-(M-362 43 Replace oil 45 2E12-C3000 (RN)

Lubricate coupling ,

31 Div !!! RRR Repisco eil 82 28 RHR WS Strainer Perform SQ inspection 65 2512-F0528 (RH)

Perform RQ inspection 2E12-F0063 (RM) 96 Perform breaker inspections and

) 2A D/G replace contactor for 20001P 97 Clean discharge pipe fittlag 2A D/C 011 Pump pp calibrate relay 2C RHR Pump 99 Clean eteler 100 2C RMR Sssi-cooler Closa cooler 8 RHR 102 Test relay 3 RNR I 103

~ _ . - - -- _

m w7ava mm . Mw

..i-

• b Changes to the Off-Site Does C;1e:14 ties Maasta (sone l '.

4. Major changes to Radiotetive Waste treatment Systems.

(Nose)

5. Indications of railed Fuel B1emente.

(None)

I I

l n

i

)

i i i

I

+

1 9

l-i

a

e 3CADTS/7 e+ + . - <v .. , _- . , , , , . _ _ , . _ , , , , . . . . . . - . . - , . . . . . . -