Text

Monthly Operating Repts for Jul 1991 for LaSalle County Nuclear Power Station
	ML20077P072
Person / Time
Site:	LaSalle
Issue date:	07/31/1991
From:	Cialkowski M, Diederich G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	NUDOCS 9108150242
	Download: ML20077P072 (24)
	v • d • e

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N C:mm:nw :lth Edis:n

) Rutalnoute 81, Box ??O LaSetle Coumy Nu;!r:ar Station c;

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, t/arsedles,likne<s 0134i U

qj T0!cphone 815/357 6761 August 10, 1991 l

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station P1-137 Hashington, D.C.

20555 ATTH: Document Control Desk j

i Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for July, 1991.

Very truly yours,

m 0 [; '3M hf.J.Diederth G

Station Hanager LaSalle County Station GJD/HJC/bkw Enclosure xt:

A. B. Davis, NRC, Region III T. H. Tonque, NRC Resident Inspector LaSalle J. L. Roman, IL Dept of Nucicar Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. farrar. CECO INPO Records Ccnter D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Naughton, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisar H. H Servoss 0A/NS Off Site Review Station file ZCADTS/5 910g17,0242 91o*/31 05 cog:73 f 6') If.

{DR ADock If /

1 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE R'a0RT JULY 1991 COMMONHEALTH EDISON COMPANY i

NRC DOCKCT NO. 050-373 LICENSE NO. WPF-11 1

ZCADTS/S

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TABLE OF COMIENTS GJNIT 1) 1.

INTRODUCTION g-II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE

[

B.

AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATI0HS C.

HAJOR CORRECTIVE HAINTENANCE TO SAFE 1Y-RELATED EQUIPMENT 0.

LICENSEE EVENT REPORTS

(

E.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions F.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valva Operations 2.

ECCS System Outages t

3.

Off-Site Dose Calculation Manual Changes r%

4.

Major Changes to Radioactive Haste Treatment System 44 5.

Indications of failed fuel Elements s

ff 8

K

)

E o

7 ZCADTS/5

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1.

-INTRODUCTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles Illinois.

Each unit is a Boiling Mater Reactor with a designed net electrical output of 1078 Megawatts.: Naste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was p

Commonwealth Edison Company.

Unit'One was issued _ operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved oa June 21, 1982 and commercial power operation was commenced on January 1,1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

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l ZCADTS/5

~...

II., MONTHLY REPORT

-A.

SLM4ARY OF OPERATING EXPERIENCE (Unit 1) day Ijne Event 1

0000 Reactor _ critical, generator on. line at 950 Hwe, reducing power level to 890 Mwe due to system load.

1100 Increased power level to 1100 Mwe.

2 2300 Reduced power level to 970 Mwe due to system load, held power level due to a chattering RPS relay.

3 0100 Reduced power level to 850 Mwe due to system load.

1000 Increased power level to 1100 Mwe.

4 0500 Reduced power level to 850 Mwe due to system load.

1330 Increased power level to 1105 Mwe.

5 0200 Reduced power level to 850 Hwe due to system load.

1130 Increased power level to 1100 Mwe.

9 0130 Reduced powr level to 750 Mwe due to system load and performed rod moves.

0330 Increased power level to 850 Mwe, held power level due to system load.

1200 Increased power level to 1100 Mwe.

10 0100 Reduced power level to 850 Mwe due to system load.

1000 Increased power level to 1100 Mwe.

14 0200 Reduced power level to 850 Mwe due to system load.

1500 Increased power level to 1105 Mwe.

15 0230 Reduced power level to 840 Mwe due to system load.

1400 Increased power level to 1100 Hwe.

21 0600 Reduced power level to 930 Mwe due to system load.

1600_

Increased power level to 1100 Mwe.

22 2400 Reduced power level to 1050 Mwe to perform weekly surveillances.

23 0330 Increased power level to 1100 Mwe.

24 0400 Reduced power level to 990 Mwe due to system load.

1000 Increased power level to 1100 Mwe.

ZCADTS/5

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M.0NTHLY REPORT II.

A..

SUDMARY OF OPERATING EXPERIENCE (Unit 1) (Continued) day ling Event 26 0300' Reduced power level to 1000 Mwe due to system load.

1030 Increased power level.to 1100 Mwe.

28 0200 Reduced power level to 850 Mwe due to system load.

1200 Increased power level to 1105 Mwe.

30 0100 Reduced power level to 830 Mwe due to system load, performed weekly, monthly and quarterly surveillances.

1330 Increased power level to 1105 Mwe.

31 0100 Reduced power level to 850 Mwe due to system load.

1100 Increased power level to 1110 Mwe.

2400 Reactor critical, generator on-line at 1110 Mwe.

.ZCADTS/S

'll.

AMENDMENTS TO THE FACILI1Y LICENSE OR TECHNICAL SPECIFICATION (None)

C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED E()UIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 1)

LER Number pitt Description 91-010-00 07/19/91 Control Room HVAC system and Auxiliary Electric Equipment Room ventilation emergency make-up fan OVC03CA auto started on a spurious trip of Control Room air intake radiation monitor.

91-012-00 07/29/91 RCIC system turbine tripped on overspeed due to turbine governor valve failed to close during performance of RCIC cold quick start testing.

E.

DATA TABULATIONS (Unit 1) 1.

Operating Data Report (See Table 2) 2.

Average Daily Unit Power Level (See Table 3) 3.

Unit Shutdowns and Significant Power Reductions (See Table 4) l.

l i

ZCADTS/5

C.

TABLE 1'(UnitL1)

MAJOR CORRECTIVE MAINTENANCE TO.

SAFETY-RELATED EQUIPMENT:

^

MORK REQUEST RESULTS AND EFFECTS i

NUMBER COMPONENT CAllSE OF MALFUNCTION

'ON SAFE PLANT OPERATION CORRECTIVE ACTION

~

LO5898 Control Room HVAC Actuator Motor' seal Degraded damper. operation.

Rebuilt actuator.

L Temperature Control leakage i

Damper OVC22YB.

i LO8524 High Pressure Core.

Mater leg. pump.

Degraded operation.

Rebuilt pump.

LSpray Mater Leg Pump IE22-C003 LO8995 Hydraulic Control Mater charg*ng nipple Degraded control rod operation. Replaced charging nipple.

j Uni t ~ 10-43 leaking.

i LO9005 Hydraulic Control Instrument block valve Degraded control rod operation. Replaced valve cartridge.. I Unit 10-43

' leakage.

+

j.

i LO9127 Scram Discharge

'B' Pilot solenold.

None.

Replaced solenoid coll.

Volume Vent and

' Drain Valve.

LO9249 Average' Power' Range Quad trip card.

Initiated half scram.

Replaced quad trip card..

Monitor 1F.

L80365 Control Rod Drive Pump Erosion of pump casing.

None.

Rebuilt pump.

IC11-C001B (No SOR failures this month.)

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ZCADTS/5+

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^

E.3 UNIT-SHUTf10 MIS AND PONER REDUCTIONS > 201-(Unit 1):

1

METHOD OF

. CORRECTIVE-YEARLY

. TYPE SHUTTING DOMN ACTIONS / CON 4ENTS

. SEQUENTIAL'DATE-'

F: FORCED

. DURATION THE REACTOR OR

-(LER/DVR # if NUMBER (YYMOD) 5: SCHEDULED' (HOURS).

REASON REDUCING PONER.

applicable)

-(None) i t

SlM4ARY OF OPERATION:

The Unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, surveillances and maintenance activities.

4 ZCADTS/5

-Q.

F., UNIQUE REPORTING REQUIREMENTS (Unit-1) 1.

Safety / Relief valve operations

. VALVES NO & TYPE-PLANT DESCRIPTION 081E ACTUATED ACTUATION 00NDITION OF EVENT (None)-

2.

ECCS System Outages (See Table 5) 3.

Changes to the Off-Site Dose Calculation Manual (None.)

4.

Major changes to Radioactive Naste Treatment Systems.

(None)-

5.

Indications of failed Fuel Elements.

(None)

L l

l i

ZCADTS/S

. - ~.

f:+.

(Unit 1) i

-Table 5 F.2 ECCS System Outages

~

Note: -The year and unit data has-been removed from the outage number.

OUTAGE NO.

-LOUIPMENT ISRPOSE L(U-0)

'242 00G01P Lubrication

- 245 t 00G01K Callbrations (U-1):

1404 1E22-C003-Replaced Hater Leg Pump 1417

.1E12-C003.

Lubrication, j-1418 l

l, b

e:

l-l

)

ZCADTS/5+

LASALLE hUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JULY 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

l-ZCADTS/7

.c c.,,

4 TABLE OF CONTENTS (Unit 2)

I.

INTRODUCTION II. REPORT.

A.

SU MARY OF OPERATING EXPERIENCE B.

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D.

LICENSEE EVENT REPORTS E.

DATA' TABULATIONS

1..

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit-Shutdowns and Power Reductions F.

' UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Racioactive Maste Treatment System 5.

Indications of Failed Fuel ~ Elements ZCADTS/7

g a

+

9 I.

INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois.

Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts.. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit Two was issued operating license number NPF-18 on December 16, 1983.

Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

t i

l ZCADTS/7

j II.., MONTHLY REPORT A.,

SU MARY OF OPERATING EXPERIENCE (Unit 2) day lbst Event i

1 0000 Reactor critical, generator on line at 1100 MWE.

3 0130 Reduced power level to 1075 Mwe to transfer the Condensate / Condensate Booster pumps.

0700 Increased power level to 1100 Mwe.

5 0200 Reduced power level to 850 Mwe due to system lesd.

1130 Increased power 1cvel to 1100 Mwe<

9 0430 Reduced power level to 970 Mwe due to system load, performed weekly surveillances.

1100 Increased power level to 1100 Mwe, 13 0100 Reduced power level to 950 Mwe for rod set.

0130 Increased power level 980 Mwe, performed Monthly L

surveillances.

1100 Increased power level to 1100 Mwe.

14 0530 Reduced power level to 850 Mwe due to system load.

1200 Increased power level to 1100 Hwe.

i l

18 0200 Reduced power level to 1070 Mwe to transfor the Condenshte/ Condensate Booster pumps.

l 0700 Increased power level to 1100 Hwe.

28 0100 Reduced power level to 985 Mwe due to system load.

1145 Increased power level to 1105 Hwe.

30 040C

- Reduced power level to 1050 Mwe due to system load.

l l

1200 Increased power level 11 @ Mwe.

31 0330 Peduced power level to 950 Mwe due to system load.

1000 Inc: cased power level to 1105 Mwe.

L 2400 Reactor critical, generator on-line at 1105 Mwe.

l ZCADTS/7 t

~.

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'h.-

AMENDMENTS TO THE FACILITY-LICENSE OR TECHNICAL-SPECIFICATION

+-

. (None). --

C. -

MAJOR CORRECTIVE MINTENANCE TO SAFETY RELATED EQUIPMENT-(including-

-SOR differential pressure switch failure reports).

-(See Table 1)

D.'-

LICENSEE EVENT REPORTS (Unit 2)

LER humber DAtg Description

.(None.)-

E.-

DATA TABULATIONS (Unit 2) 1.

Operating Data Report.

(See Table 2) 2.

Average Daily Unit Power Level.

(Sec Table 3) 3.

Unit Shutdowns and Significant Power Reductions.

(See Table 4)

ZCADTS/7

C..... TABLE 1 (Unit 2)

~

MAJOR CORRECTIVE MAINTENANCE TO-SAFETY-RELATED EQUIPMENT HORK REQUEST-RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION

. CORRECTIVE ACTION LO3087 Main' Steam Isolation Instrument:stop valve-None.

Replaced valve.

V,11ve Leakage Control 2E32-F302N leaking.

Pressure Interlock LO3088 Main Steam Isolation' Instrument stop valve-None.

Replaced valve.

Valve' Leakage Control 2E32-F309_ leaking.

Pressure Interlock LO3089 Main Steam Isolation.

Instrument stop valve None.

. Replaced valve.

Valve' Leakage Control 2E32-F302A leaking.

Pressure Interlock LO3090 Main Steam Isolation Instrument stop valve None.

Replaced valve.

Valve Leakage Control l2E32-F302E leaking.

Pressure Interlock LO3091 Main Steam Isolation Instrument stop valve Mone.

Replaced valve.

Valve Leakage Control 2E32-F302J 1eaking.

Pressure Interlock LO8692 Control Room HVAC Filter paper drive motor.

Detector inoperable.

Replaced drive motor.

Ammonia Detector OXY-VC165B (No SOR Failures this month.)

ZCADTS/7 t

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'I N
' E.3 '. UNIT SHUIDONNS AND POWER REDUCTIONS >204-
~
I
'(UNIT.2)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /C0peGENTS SEQUENTIAL DATE-F FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YDe(DD) St SCHEDULED (BOURS)
REASON REUQGING PQWER applicable)
-(None)
SUDNARY OF OPERATION:
i The unit remained on line at high power throughout the month. Several minor. power reductions were required due to system loading and routine surveillances.
i i
e f
ZCADTS/7 i
g.
~
F..
IJNIQUE REPORTING REQUIREMENTS (Unit 2)-
1.-
Safety / Relief Valve Operations-
-VALVES NO & TYPE PLANT DESCRIPTION 061(
6CTUATED.
-bgTUATIONS-CD@UJDi 0F EVENT (None) i ECCS System Outages 2.
(See Table 5.)
3.
Changes to.the Off-Site Dose Calculation Manual.
(None.)
4.
Major changes to Radioactive Maste Treatment Systems.
(None)-
5.
Indications of Failed fuel Elements.
-(None)
Q r
ZCADTS/7
a.
(Unit 2)
Table 5 f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO.
E0VIPMENT PURPOSE 266 2DG006 Repair cooler outlet valve.
282 2E22-C002 Meggar motor.
288 2E22-S001 Replace soak-back oil filters.
297-2E51-f045 Perfora survel11 ante LES-EQ-112.
2E51-F046 301 2E51-C003_
Replace MCC contactor.
335 20G011 Inspection.
f ZCADTS/7 l~
N u
s w'

ML20077P072

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