ML20006G124

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Monthly Operating Repts for Jan 1990 for LaSalle County Nuclear Power Station Units 1 & 2
ML20006G124
Person / Time
Site: LaSalle  Constellation icon.png
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)
v • d • e


Text

86/26/mi 31151 NO.083 P002 i

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Lale le County Nucleer 3 stion

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RUW butee1. Sea 240 MeteNIles,Ithnet$1341 l

' Teleghone 416/38F 6761

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i Februsty 10, 1990 I

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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 information la the monthly performance report covering Enclosed for your j

LaSalla County Nuclear Power Station for January, 1990.

t i

Very truly yours, e.

l.

j

0. J. Diederich 1

hgStationNapager f

l Lass 11e County Station i

l-GJDIJWT/psk i

F.ncIosute set)

A. D. Day (0, NRC, Region I!!

NRC Resideat Inspector LaSalle I

111. Dept.

of Nucient Safety l

P. Shemnus ti. NRR Project Manager e

l D. P. Oslla, Ceco D. L. rarr ar, Ceco l

2NPO Recor $s Center tasia, AIP Coordinator, Nuclear Services L. J. Anas 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 INPO Coordinator, LaSalle Station Terry Novotney, T.A.Hmperich, Regulatory Assurance Supervisor i

J. W. Glaselter, Technical Staff Supervisor

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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

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

TABLS OF CONTENTS I

1 1.

INTRODUCTIGl 11.

REPORT A.

$1#06 arf 0F OPERATING EXPERIENC8 3R PROCEDURE CKANGts, TESTS, RKPERIMENTS, AND 5&FETT RELATED B.

PLANT RANCE mendments to Facility License or Technical Specifications NAINTE 1.

A hanges to procedures which are described in the safety 2.

C l

nalysis Report ests sad Esperiments not covered in the Befety Analysis Report A

3, 1 orrective Maintenance of Safety-Related Equipment 4.

C ompleted safety Related Modifications 5.

C I

C.

LICEMi>Et EVENT REPORTS

+

D.

DATA MADULATIONS yerating Data Report 1.

taverage Daily Unit Power Level 2.

Unit Shutdowns and Power Reductions 1.

1 F..

UN100 5 REPORTING REQUIREMENTS dain Steam polief Valve Operations 1.

i ECCS System Outages 2.

Off Site Dose Calculation Manus! Changes 3.

dajor Changes to Radioactive Weste Treatment System 4.

Indications of railed Fuel Elements l

5.

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i 1.

INTRODUCTIGI County Nuclear Power Station is a two. unit facility owned by Each The LaSalle h Edison Company and located near Marseilles, Illinois.

sillag Water tooetor with a designed met electrical output of Commonwoolt Weste heat je rejected to a maa-ande coe11ag pond uslag unit is a a The architect-engineer was 1076 Negawatts.

s River for make-up and blowdows.

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

17, 1962.

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

was comp!!ad by John W. Thunstedt, telephone number This report (815)157 61 61, entension 2463.

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86/26 4 :

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MCIIT1tLY RSM*T A.

SUDe4ARO OF OPERATING EKFSRIEllCE Dag 1h E_vant Reacter suberitical, generator off-lise, L1803 in 1

0 >00 progress.

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

7 3215 9

0045 Reactor critical 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 Reduced power to 1802 MWT for control' rod alignment 16 0200 LOOO Increased power to 2900 MWT Reduced load to 2761 MWT for CRD maintenance 16 2230 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'

27 0700 Returned to full power 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 f-1200 Returned to full power i

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gar MRe Reduced power to 993 Nws for CRD esereleing 30 0000 1100 Returned to full power teactor critical, generator on-line et 1130 Mw8.

31 34 00 R PROCEDURE CHAlt058, T8875, EEP8RIMENTS AND SAFETt StLATED j

9.

PLANT O NA!NTallANCE.

ienements to the Facility License or Technical specificaties.

1.

M avision to the Pressure / Temperature curve referenced in DT9chnical Specification 1/4.4.6.

4anges to procedures which sto described in the Safety 2.

C Analysis Report.

LP-89-012 " Unit 1 Operation with RPV Flange Seal Leak" L

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

1 esting" This procedure provides the methode and controls to allow

  1. ~'

bypassing the Unit 1 Rod Sequence Control System during control rod scram testing above 20% power.

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

r toport.

None) 4ajor corrective maintenance to Safety-Related Equipment.

4.

(see Table 1)

ompleted Safety-Belated Modifications.

5.

(See Table 2) v 2CADTS/5

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O.4-Tama 1 3.-

g muon conneenet NarmEsamer to s

t SArETT-RELATED SQU1FDENT

    • sm-ts amo crrscTs ConseCTITE acTIm

.ON SAFE PLANT OPERATIm g

i woan meoutsr CAUSE OF MALFUNCTION E

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Cose'ONENT NUseER 4

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(geone) l (Galt 1)

Beplaced switch

~Bigh Pressure" alarm Internal failure L95251 0 D/G Crankcase activated 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 Excessive wear l

Persommel access L96557 hatch outer door hanemheel shaft seal ZCADTS/5

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i tC.013 P009 06/86/4:

31:52 s.l TAsLE 1 l

courtg7so skrsvr-a:LArso woorricAttons i

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_sesentestou

=.. a tallaties of a pasonry wall steel support columa, N01 0-se-001 1s s i

and in intended to provide 1steral sopport for Seismic et,i 71 0togory :t masonry wall panel.

Co stallation of a " Local-Remote" transfer evitch and a new s control circuit fuses to esisting switchgear brooker M01 1-87-008 In ntrols for the D/0 "0" CNP OD001P Feed Brothers.

on l

co stallation of a local-Romote" transfer switch and a new s l

l control circuit fuses to esisting switchgear brooker M01 1-87-011 1

of ntrols for ESS Division 1 Feed trookers.

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nstallation of a " Local-Remote" transfer switch and a new t control circuit fuses to esisting switchgear brenner N01-1-87-014 I

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

c nstallation of " kill pushbuttons" and rearrangement of ecorders and recorder pens for the 1N13-P602 panel in M01 1-87-028 I

r ccordance with Human Factors.

a pilt annutciator lato two esparate alarm windows for the high nd low pressure alarms to allow Control Room O M01-1-87-029 s

o o

panel in accordance with Human Factors.

hearrangement of the Vent and Purge damper controls located on i h Humma

,PM06J into a logical configuration in accordance w t M01-1-87-030

" actors.

)

bypass valve f

[nstallation of an alarm to indicate that turbine is open located on 1PM02J panel in accordance with Ruman M01-1-87-033 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 to reduce neutron and gamma radiation streaming at reactor M01-1 87 094 building elevation 766'-6.

pep acing the existing 125 Volt, Division 1 b l

M01-1-88-004 for the bettery and it's associated charger.

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

M01-1 88-030

/B valves, Replace the double configuration, for the 1933-F067AThe existing M01-1-89-001

  1. 1erible wedge disc.
  • a."

^a disc to be

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12. AtACTOR $tiv!CE FAC108 (1) 83.6 83.1 64.4
n. aucw....s ue s,,..r e 69.5 H.5 59.8
14. Stev!CE FACTOR di et.e

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17. CAPAt11Y N.10R (U$!NG D($1GN Mfe) (2) 14.4 16.4 it.i
19. FORCO OUTAct FACfot 1:
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REASON isinn.un, n--

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NEBSEE DATE S: SneumOLED Befueling Outage (L1383) 4 1

278.3 C

1 9/15/09 5

Unable to synchroeles 4

generators sketdeus reacter 60 B

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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

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INTRODUCTICR i

d by k 3dioen company and located nest Marseilles,1 Each The 1,65a110 i l output of

%1 ling Water Reactor with a designed met electr caW commeswes14 unit is a The arebitect-engineer was atts.

1018 Megaw le River for make-up and blowdown.

j t Lundy and the primarr constructies oestracter was the Illino Sargent am Commonwealth Edison company.

b 16, as issued operating licones number NPr.18 en Decem er 10, 1944 and commerc ail tial criticality was achieved on March Unit Two w 1943.

Ini 19, 1984.

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

This repoi 1

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31:03 NO.013 pgg7 I k.'. ',

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i TABLE OF COWTENTS l

g.

INTpaccCTIC N f

11.

REPORT Y OF OttEAT1MO EEPERIENCE A.

S u m Alt OR PROCEDURE CHANGES, T8878, EXPERIMEWFS, AND SAPSTY S.

PLANT kmendments to racility License or Technical Specifications NANCE Nh!NTB Changes to procedures which are described in the Safety 1.

2.

Tests and Esperiments not covered in the Safety Analysis Report.

Analysis Report.

l Corrective Maintenance of Safety-Related Equipment 3.

4.

Completed Safety Related Modifications b

5.

C.

LICD SEE EVENT REPORTS D.

DATA TA5ULATIONS Operating Data Report 1.

Average Daily Unit Power Level 2.

i Unit Shutdowns and Power Reductions l

  1. ~'

3.

JE REPORTING REQUIRENENTS E.

UNIQ Safety / Relief Valve Operations 1.

ECCS System Outoges 2.

Off-site Dose Calculation Manual Changes J

Major Changes to Radioactive Maste Treatment' System 3.

4.

Indications of Failed Fuel Elements 5.

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Or OFREATimo EEPERIBICE A.

SUD9&M T m

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h Reactor criticti, generator en-lies at 3050 tert.

1 9000 Returned to full power f

1400 Reduced power to alle Wrt for CR0 esercising and 3

D100 System lead Returned to full power 1400 Reduced load to 2950 Mr! for System lead 0200 4

Returned to full power 1200 Reduced load to 2910 Murt for CRD esercieing l

10 0000 Returned to full power i

1300 3

Reduced load to 3040 MWT for System lead 14 0230 Returned to full power 1500 Reduced load to 2930 MIrf for System load 16 0230 I

Returned to full power 1200 f

Reduced load to 3100 MfT for surveillances 2330 Returned to full power 17 1000 Reduced load to 3551 MWT for System load 19 2300 Increased power to 3266 MWT 21 0100 Reduced lead to 2990 MNT for System lead 0200 Returned to full power 22 1100 Reduced power to 2523 MNT for CBD esercising i

0300 24 l

Returned to full power 1600 Reduced power to 3020 MWT for flow-control-line j

31 0020 evolustion Reactor critics), generator on-line at 3154 MwT 2400 1

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3 EptatMENTS AND ShrBTW atLhTED

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3 ptJJrt 08 McCSDUtt CRANO38, 73578, I

MAINTENANCI ents to the Feellity License er Techniss1 Spesifiestles.

{

l7 1.

' Ament es to the Temperature Pressure curve reforested in Techniesi SevisL Spectlicaties 3/4.4.6 f

es to procedures which are described is the Safety haalysis

[

'3.

Chang Report.

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

overl ession Pool valve 3E33-P013.

Suppi-and Esperiments act described la the Safety haalyste Report.

f 3.

Testo (Hone) r corrective maintenance to safety-Related Equipment.

4.

Majo (Nost) i leted safety-Related Modifications.

5.

comp (See Table 2) l l

C.

LICENSEE EVENT REPORTS f

(None) i D.

DATA TAWTLATICMS 1

ting Data poport (Attached)

1. Opera 1

ge Daily Unit Power Level (Attached)

2. Avera Shutdowns and Power Reductions (Attached)
3. Unit r

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13. ADCt0ft AVA!LA>1LifY f ACTO' m IM,9 1M.4 65.4
14. 5ttV!CE FACIOR 0 ;

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

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

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(Neme) 2.

ECCS System Outages ggapaan erstr_ ent

=

stant no.

and unit numbers have been ensnitted from the Outogo Number)

(Notes the yes i

11lmit 0)

Replace pressure switch 0 D/0 20 I

IUnit 1)

(Administrative)

B RNR 8

(Admlaistrative)

& RHR 18 Over speed testing RCIC 20 Repisce relay to test CY valve IE51.F059 (RI) 48 Defeat spurious isolation signals i

RCIC Steam riow 54 Line-break detection (Administrative) 1E12.F006 (RH) 58 Check hold-down screws 1D008CA

$9 "A" Air Compressor

(

Inspect strainer i

I 15 D/G Cooling l

66 Water (MP)

Lubrication 18 D/0 67

(

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

(None).

)

Major changes to Radioactive Waste Treatment Systems.

4.

(None).

Indications of railed fuel Elements.

5.

(None) r

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1. Safety /Itelief Valve Operatione Wh',#58 NO & TYPE PLANT DESCRIPT!W acutfAT1 cats cearntricas or aven, _

I ggg gggggs 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 RNR WS Cooler Fans Replace costector 5

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

24 r

Repair compressor 2DC03CA 28 Perform 50 laspection 2E12-F0268 (RM) 31 Perform inspection 2E12-F094 (RN) 35 Perform L85-SQ-112 2C12-F094 (RH) 36 g

Perform R$ inspectica 2E12-F0268 (RH) 37 Inspection 2D008CA 38 Lubricate couplings, cleas coolers 2A RHR SW 41 Perform 128-(M-362 2A RRR Pump 43 2E12-C3000 (RN)

Replace oil 45 Lubricate coupling Div !!! RRR 31 28 RHR WS Strainer Repisco eil 82 Perform SQ inspection 2512-F0528 (RH) 65 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 2C RMR Sssi-cooler 100 Closa cooler 8 RHR 102 Test relay 3 RNR 103

~

m w7ava mm Mw

..i-Changes to the Off-Site Does C;1e:14 ties Maasta b

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Major changes to Radiotetive Waste treatment Systems.

4.

(Nose)

Indications of railed Fuel B1emente.

5.

(None)

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3CADTS/7 e+

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