ML20034A628

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Monthly Operating Repts for Mar 1990 for LaSalle Units 1 & 2
ML20034A628
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/31/1990
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9004240022
Download: ML20034A628 (25)
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Y Commonwealth Edison.

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) - LaSalle County Nuclear Station

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-. _ _. y' ReralRoute #1. Box 220 '

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. --Telephone 815/357 6761-April 5, 1990 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station P1-137' Washington, D.C.

20555 ATTN:

Document Control Desk Gentlemen Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for' March, 1990.

Very truly yours,-

'b

-i G..J.- Diederich Station Manager LaSalle County' Station GJD/JWT/crh I

Enclosure xc A. B. Davis, NRC, Region III NRC Resident Inspector-LaSalle Ill. Dept. of Nuclear Safety

]

R. Pulsifer, NRR Project Manager i

l D. P. Galle,' CECO D. L. Farrar, CECO l

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INPO Rtcords Center

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D. R. Eggett, NED L

J. E. Kuskey, GE Resident T. J.

Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Fuel Services Manager C. F. Dillon, Senior Financia1' Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station T. A. Hammerich, Regulatory Assurance Supervisor i

J. W. ' Gleseker, Technical Staf f Supervisor Central File t

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'I TABLE OF CONTENTS I.

INTRODUCTION II.

REPORT A.

SUMMARY

OF OPERATING' EXPERIENCE, B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1.

Amendments to FacilityLLicense or Technical Specifications

~

2.

Changes to procedures which are described in the Safety 1 Analysis Report 3.

Tests and Experiments not covered in,the Safety Analysis Report 4.

Corrective Maintenance.of Safety-Related Equipment 5.'

Completed Safety-Related Modifications C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level l

3.

Unit Shutdowns and Power-Reductions' l

E.

UNIQUE REPORTING REQUIREMENTS

-l 1.

Main Steam Relief Valve Operations' j

2.

ECCS System Outages

]

3.

Off-Site' Dose Calculation Manual Changes l

4.

Major Changes to' Radioactive Waste Treabnent System 5.

Indications of Failed Fuel Elements j

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INTRODUCTION The LaSalle County Nuclear Power Station 18 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.- Waste 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 One was issued operating license number NPF-11 on April 17, 1982.

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

This report was compiled by John W. Thunstedt, telephone number (815)357-6701, extension 2463.

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II.

MONTHLY REPORT.

A.

SUMMARY

OF OPERATING EXPERIENCE

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Day Ilme Event 1

0000 Reactor critical generator on-line at 3320 )DCr.

5 2400 Reduced load to 3000 MWT for CRD exercising.

6 1300 Returned to full power.

l l

12 0200 Reduced load to 3090 MWT for System load.

~

1000 Returned to full power.

13.

0030 Reduced load to 3190 for CRD. exercising.

0700 Returned to full power.

14

_0200 Reduced load to 2970 MWT for System load.

1000 Returned to full power.

15 0200 Reduced load to 2530 MWT for System load.

1000 Returned to full power.-

20 0030 Reduced load to 3174 MWT for CRD exercising.

1000 Returned to full power.

21 0400 Reduced load to 2500 MWT for Surveillances and control-rod moves.

i 1200 Returned to full power.

22 0000 Reduced load to 3000 MWT for System load.

1000 Returned to full power.

24 1230 Reduced load to 3181 MWT for cooling problems on 1W Main transformer.

1600 Returned to full power.

27 0000 Reduced power to 3125 MWT for CRD exercising.

20 0340 Reactor scram, generator-trip, due to failure of an insulator on 1W Main transformer.

30 0030 Reactor critical.

31 0310-Generator on-line.

2400 Reactor critical, generator on-line at 2216 MNT.

ZCADTS/S

4

..' s B.

PLANT OR PROCEDURE CHANGES, TESTSi EXPERIMENTS AND SAFETY RELATED' MAINTENANCE.

1.

Amendments to the Facility License or Technical Specification.

I a.

Clarified DG Start requirements.

b.

Clarified DG fast-start / load requirements..

c.

Revised DG: test schedule per Generic Letter.

t 2.

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

a.

LaSalle Special Procedure LLP-90-014, " Operating Procedure Votes 100. System".

This procedure providos instruction.

for the periodic testing of valve operators using the Valve Operation Test and Evaluation System (VOTES).

b.

LaSalle Operating. Procedure LOP-RH-07, " Shutdown Cooling _.

System Startup and Operation."

Addition to Limitation and Actions to allow the use.of.

l 1(2)E12-F065A/B RHR Heat Exchanger Steam Condensing Outlet I

and,1(2)E12-F0llA/B, RHR Heat Exchanger Steam Condensing to Supp. Chamber Stop Valves for Reactor. Vessel Level i

Control / Water-inventory.

l 3.

Tests and Experiments not described in the Safety Analysis Report.

l (None) t.

l 4.

Major corrective maintenance to. Safety-Related Equipment, including any SOR switch failure reports.

(See Table 1) 5.

Completed Safety-Related Modifications.

(See Table 2) i ZCADTS/5 f

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' TABLE 1

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....t. u MAJOR ~ CORRECTIVE MAINTENANCE..TO i

SAFETY RELATED EQUIPMENT WORK' REQUEST

.RESULTS AND EFFECTS-4 NUMBER COMPONENT CAUSE OF MALFUNCTION

ON SAFE PLANT OPERATION:

CORRECTIVE ACTION, _

j.

(Unit 0)

None (Unit 1)

L97999 Personnel Worn excessively

' Leakage past seal.'

Replaced : seal

air-lock outer door upper shaft-seal.

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J (No SOR Switch' Failures)

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NUMBER DESCRIPTION

.)

M01-0-88-002 Relocate the Reboller Leak Detection Radiation Monitor 1(2)D18-K752 to the far right of the radiation monitor grouping for the Control Room HVAC Intake Radiation Monitors. This is I

performed in accordance with Detailed Control Room Design Review (DCRDR).

M01-0-04-111 Installation of the HACR-IV synchronizing check relay in place of the existing Westinghouse CVE synchronizing check relay and its associated wiring.

M01-1-86-083 Replace existing Reactor Water Clean Up (RWCU) Lonegran relief valves 1G33-F340A and 1G33-F340B with slow-opening valves.

M01-1-87-027 Relocate the oxygen breathing lines which have created,a

-tripping hazaed for control room personnel. This is performed in accordance with Detailed Control Room Design Review (DCRDR).

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LICENSEE EVENT. REPORTS LER Numbar Date Dagdr. lotion -

90-005-00 03/27/90'- Fire Detection Zone OOS >'14 Days-and no special report submitted.--

, 006-00

-03/28/90 Reactor Scram Due to Loss-of Main Transformer.

D..

DATA TABULATIONS

1. -- Operating Data Report (attached)'~

2.

Average Daily,-Unit Power ' Lewl ' ( attached).

3.

Unit Shutdowns and Power Reductions'(attached) g ZCADTS/5

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lD.1 J0PERATING MTA REPORT--

DOCKET NO. 050-373

UNIT LASALLE ONE MIE Aprit 10i 1990; j

7-COMPLETED BY J.W.' THUNSTEDT -

TELEPHONE'(815)-357-6761 OPERATING S1AIUS ili-REPORTING PERIODL MARCH 1990

GROSS HOURS IN REPORTING PERIODt 744i 2i-CURRENTLY AUTHORIZED POWER LEVEL thWI):

3,323

-NAX DEPEND CAPACliY (hWe-Net):

1,036 <-

DESIGN ELECTRICAL RAllNG (MWe-Net) 11,078 :

4 3. - P06'ERlEVEL 10 'WHICH RESTRICTED i!F ANY) (NWe-h'et)f

. (None)'

.c 4.1 REASONS FOR RES1RICi10NI(If ANY):-

(N/A) 4

REPORTING PERIOD' DATA?

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-THISMONTH-

- YEAR-10-DATE-

'COMULATIVE

5. ' TINE REACTOR CRITICAL'(HOURS)
699.11
1,989.0 l
34,123.1' 6.L llME REAC10R RESERVE SHUTDOWN (HOURS) 0.0 -

0.0 1,641 ~ 2

'7.

11PE GENERA 10R DN-LINE (HOURS)

.'672.5

't,862.1 I T33,200.41

-l8.~ IINE GENERAIDR RESERVE SHU100W (HOURS)

' O.0 0.0 '

(1'.0 ;

9.1 THERhAL ENERGY GENERATED (MWHt-Gross) 2,172,000 5,726,279.4:

93,559,847.4j 10.ELECTRICALENERGYGENERATEDthWHe-Gross) 740,756-31,951,380l dint?,921/

M

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11. ELECTRICAL ENERGY GENERATED (MWHe-Net)

'715,591?

i,884;422i 29,s17,124

12. REAC10R SERVICE FAC10R~(%)

94.0.

- 92.1 L62.3~

13. REACTOR AVAILABILITY FACTOR (%)

.94.0 Y2.1; f 65.3 ~

14. 3ERVICE FACTOR (%)

90.4 :

86.2 s

'60.1 l'

- 15. AVAILIBILITY FACTOR (%)

90.4 !

' 86;2 1 60.7.

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16. CAPACITY FAC10R (USING MDC)-(%)--

. 92.8 :

84.2~

52.24 lt?[CAPACITYFACTOR(USINGDESIGNHWe)(%)

89.2 (80.91

50.1-'

El8iFORCED00TAGEfACTOR-(Zi 9.6 6.6 --

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1 A.]y "19. SHUTDOWS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)t (None)

20.-IF SHUIDOW Al END OF REPORT PERIOD, ES11 MATED DATE OF STARTUP

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4 DOCKET N0!_050-373.T,

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NUMBER-DATE

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REASON REDUCING POWER'

' ACTIONS /COME3rIS.

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E. UNIQUE REPORTING REQUIREMENTS'

1. ' Safety / Relief valve operations VALVES NO & TYPE-PLANT :

DESCRIPTION' DATE ACEATED ACEATION CONDITION Qf_ EVENT

- (None) 2.

ECCS System Outages

- GlTAGEA EQ'J1PMEHI P31RPOSE

'(Note the year and unit _ numbers' have been ommitted from the Outage-Number):

JUnit 0)

(None) 1 Unit _1) 139-

'RCIC

( A&ninis trative ).

J 140 RCIC Inspect brushes 141 RCIC Replace oil on Water-Leg Pump; 148 1E12-C300C(RH)

Lubricate coupling.

~152 1DG01K

_ Replace air-start motor 155-1E12-C300A(RH)

Lubricate 1couplingf 156 1E12-C200B(RH)

. Lubricate'~ coupling 157 1B D/G

Replace oil 181 1DG035 (LP)

'(Administrative) j 3.

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

4.

Major changes to Radioactive _ Waste Treatment Systems.-

3 (None)

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5.

Indications of ralled Fuel Elements.

(None) i i

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j 1 TABLE OF CONTENTS

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I.

. INTRODUCTION I

II.

REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B.

PLANT.OR PROCEDURE CHANGES, TESTSi EXPERIMENTS,D AND SAFETY RELATED MAINTENANCE 1.

Amendments to' Facility: License or Technical Specifications

~

2.

Changes to procedures which are described in the Safety -

Analysis Report.

3.

Tests and Experiments.not covered'in-the Safety Analysis. Report.~

]

4.'

Corrective Maintenance of Safety-Related Equipment 3.

Completed Sr.fety Related Modifications l

lI I

C.

LICENSEE EVENT REPORTS i

D.

DATA TABULATIONS-

^

1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS-1.

Safety / Relief Valve' Operations 2.

ECCS System Outages 3.,

Off-Site Dose Calculation Manual Changes _.

4. i Major Changes to Radioactive Waste Treabment System 5.

Indications of Failed Fuel Elements l

f i

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ZCADTS/7 i

4 T

4 I.

INTRODUCTION 1

The LaSalle County Nuclear Power Station is a-two-unit facility owned by i

Commonwealth. Edison Company and located near Marsellies, Illinois.

Each unit is a Boiling Water Reactor with a designed net l electrical output of 1078 Megawatts. Waste heat-is rejected to a man-made cooling pond using 5

the Illinois River for make-up and blowdown.

The architect-engineer was Sargent and Lundy and the primary construction contractor was i

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 complied by John W. Thunstedt, telephone number (815)357-6761 extension 2453..

5 m

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I ZCADTS/7 l

Ii.t MONTHLY REPORT _-

A.

SUMMARY

OF OPERATING EXPERIENCE f

day Timt

'EYAnt l

0000 Reactor critical, generator on-line at 3275 MWT.-

1 6

2400 Reduced load to 3000 MWT for CRDfexercising.

7 1300 Returned to full power.

]

13 0300 Reduced load to 2690 MWT for Motor-driver Reactor I

feed-pwnp test.

1300 Returned to full power.

2300 Paduced power to 2910 MWT for CRD exercising.-

l 14 1600 Returned to full power.

17 0028 Generator off-line, Refueling outage (L2R03)' began, 0118 Reactor manually shut-down (subcritical)-

31 2400 Reactor subcritical, generator off-line,.L2R03 in progress.

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to the Facility License or Technical Specification.

r a.

Clarified DG Start requirements.

b.

Clarified DG fast-start / load requirements.

c.

Revised DG test schedule per Generic Letter.

'2.

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

a.

LaSalle Special Procedure LLP-90-014, " Operating Procedure l -

Votes 100 System".

This procedure provides instruction for the periodic testing of valve operators using the Valve Operation i

l Test and Evaluation System (VOTES).

b.

LaSalle Operating Procedure LOP-RH-07, " Shutdown Cooling-System Startup and Operation."

Addition to Limitation and Actions to allow the use of 1(2)E12-F055A/B RHR Heat Exchanger Steam Condensing Outlet'and 1(2)E12-F0llA/B, RHR Heat Exchanger Steam Condensing to Supp.

Chamber Stop Valves 'for Reactor Vessel Level Control / Water; inventory.

3.

Tests and Experiments not described in the Safety Analysis Report.

(None) 4.

Major corrective maintenance to Safety-Related Equipment, including any SOR switch failures.

(See attached report for SOR 2E31-N0llD) l S.

Completed Safety-Related Modifications.

l (None) l l

ZCADTS/7

v SOR do Switch Failure Data Sheet Equipment Piece Number: 2E31-N011D Model Number 102AS-B305-NX-JJTTX6

' Serial Number 1 :86-8-1916 t

Application:

Main Steam Line Hioh Flow Isolation Switch Date and Time of Discovery: 03/27/90 Q1QQ hours.

Reactor Mode 5 (Refuel)

Power Level:

0%

Calibration Tolerance:

122_Q - LQL.Q PSID J

Nominal Setpoints 103.0 PSID Action Limits:

<ja l or >107,8 PSID Re]ect Limits:

<2id or >111,2 PSID,

Technical Specification Limit:

116,0 PSID

^

As found Setpoint:

62 d PSID Date and Time of Return to Service: 03/27/90 Q6,lQ hours Model Number of Replacement Switch:

102AS-B305-NX-JJTTX6 i

Serial Number of Replacement Switch 06-10-559 f-Cause Unknown at this time.

Susoect instrument'setooint drift.

Corrective Action:

Replaced sv. itch.

In crocess of insoectino fail'ed switch.

DVR Number 1-2-90-024 l

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[ C.1-LICENSEE. EVENT REPORTS.

s 1&R_Humhar.

Datei

Descrinilon4 90-003-00
-

03/17/90:

Inb rd. Shutdown Cooling'SDC Iso 1'ation)

- duringF-initlation of' Shutdown _ Cooling 90-004-00~

03/20/90-

' LLRT Minimum Path-Failure of,>0.6LA.

i D.

DATh~ TABULATIONS ~

1.' Operating Data Report (Attached)-

~

2. Average l Daily Unit Power Level:(Attached)-
3. Unit Shutdowns and Power' Reductions-;(Attached)"

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= D.1 OPERATIE DATA REPORT DOCKET NO. 950-374i

UNIT LASALLE TWO-s P

DATE April 10, 1999)

COMPLETED BY J.W.THUNSTEDi~

r

= TELEPHONE (015)-357-6761-

. OPERATING STATUS'

1. REPORTI E PERIOD:

MARCH 1990 GROSi HOURS IN REPORi!E PERIODi

? 744 s

2.- CURRENTLY AUTHORIZED POWER LEVEL (M t):

3,323 NAX DEPEND CAPACliY>(Me-Net)t--.

i i,036 e

-n DESIGN ELECTRICAL RAllNG'( Me-Net)'

"1,078 -

g f3. = POWER LEVEL TO WHICH RESTRICIED (if ANY) ( Me-Net):

-0

_4.; REASONS FOR RESTRICT 10N (If ANY):

_ Refueling;(L2R03)~

REPORTIE PERIOD DATA --

-THIS MONTH

' YEAR-T04 ATE !

CUMULATIVE

3. : TIME REACTOR CRiilCAL (HOURS)-

305.3

.1,764.13

31,911.2J

= 6.-

TIME REACTOR RESERVE SHUIDOW (HOURS) 0.0

~ 0.0 -

1,716.9 7.1 TIME GENERATOR ON-LINE (HOURS) i384.5 L 1,748;7-31,431.8-

~

8.

IlhE GENERATOR RESERVE SHUIDOW (HOURS):

0.0

0.0 --

- 0.0 -

~9.

THERMAL ENERGY GENERATED ( WHt-Gross)

L iii85,984 ~

5,586,967.2' 91,907,015.21 "10.'ELECIRICAL ENERGY GENERATED (NHe-Gross)-

406,288-1,907,842.

30,358,768

-11. ELECTRICAL ENERGY GENERATED (W He-Net)

'388,613' 1,037,998 -

>29,073,3035

12. REACTOR SERVICE FACTOR (%)

151.8 81.7 166.8 -

13. REACTOR AVAILABILITY FACTOR (%)

~51.8 81.?'

-70.4 1

14. SERVICE FACTOR (1) 51.7 J

~. 81.0 "

-65.8 15.'AVAILIBILITYFACTOR(1).

51.7 l81.0 65.8 '
16. CAPACITY FACTOR (US!E MDC) (1) 50.4
82.1 -

58.7f j

17. CAPACliY FACTOR (USIE DESIGN We) (Z)-

48.5 78.9 56;4 ;

118. FORCED OUTAGE FACTOR (%)"

0.0 -

2.9-

15.7 s
19. SHUIDOWS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE,' AND DURATION OF EACH):

Refseling, (In PROGRESS), 12 Weeks n20. IF SHUIDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP:

JUNE 6, 1990-V

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METHOD OF-

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NUMBER DATE~-

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E.

UNIQUE REPORTING REQUIREMENTS:

1. Safety / Relief _ Valve Operations VALVES NO & TYPE

= PLANT DESCRIPTION.

,l DAIE-ACTUATED ACTUATIONS-CONDIT.lOH ~

OF EVENT j

(None)-

.l 2.

ECCS System' Outages

]t DUTAGE_HQ1 EOUIPMENT PURPOSE 259 LPCS flushing Water-l Install Spoolf

[

Spool Piece 268 2B D/G Repair 2D0014, 2E22-F362B.

270 HPCS Install flush line from CY 271 2VYO3C Clean Cooling' coils-272 HPCS Perform LES-HP-202 and 203 276 2E12-C003 (RH)

Inspect and clean 2E12-F084.

277 2B D/G Calibrate relays.

l 278 2VYO2C Clean. cooling' coils.'-

.L 285 2E12-F042B(RH).

Perform EQ inspection.on breaker.

287 2B D/G Perform calibrations.

I 295 HPCS Repair'2E22-F007 300 2B D/G

-Perform'LES-DG-202 404 HPCS Repair Water-leg pump:

405 HPCS Meggar motor.

406 2E22-F012(DG)

Replace contactors 423 LPCS Replace bearing oil

[

424 RHR Perform LES-GM-103 425 2E12-C300D (RH)

Replace contactor springs 431 2E12-C001C (RH)

Perform LES-GM-103 433 LPCS Replace motor bearing oil ZCADTS/7

^ '!

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QQIAGE NO.

EOUIPMENT EURPOSE-

-i

  • o 3

480

'2E12-F016B.(RH Perform EO Inspection or-breakers-Perform EO inspection

- r 484

~2E22-F319-(DG)

+-

488 2E12-C002C (RH)

Perform E0 inspection

.529 2E51-F086 (RI)-

Perform MOV' actuator inspection.

f 531 2E51-F080'(RI)-

Perform MOV actuator inspection.

536 RCIC Inspect relays 552 HP-Relocate instruments 706 RH Perform LOP-RH 709 RH

~ Perform LOP-RH-07 711 2E12-F004B (RH)

Repair operator 733

.Div III-logic (HP)

Replace level switches M

734 HP Replacc. cable and switches 767 RH (Various) 768 RH (Various).

784 HPCS Fill and-Vent system :

787 2E12-F063B (RH)

Fill Suppression Pool.

~l u

793 RH Perform modification on 2PM16J 807 RCIC (Administrative) 811 2E12-C003D (RH)

. Inspect and repair discharge checkL valve-812 2E12-C300C (RH)

' Inspect and repair discharge check valve 813 Div II (RH)

Inspect. relays.

i 817 RH (Administrative).

~

831 2E22-C001 (HP)

Perform LES-GM-106 f

i 840 2E12-F009 (RH)

Perform LES-AP-201 841 2E12-C002B (RH)

Megger motor 842 2E12-F336B (RH)

' Perform E0 inspection l.

l ZCADTS/7 i

re"

~

EQUIPMENT PURPOSE OUTAGE NO -

844, Div II'(DG)

Perform LES-RH-201 Repair 2VR05YA 851 2E12-F003B (RH),

852 2E12-F068B (RH)-

Repack valve-t 881 2B RER Pump-Remove thermocouple 882 2C RHR Pump Remove thermocouple t

. Administrative).

(

883 2B RHR Pump 885-2E12-F016A (RH)

Perform LIS-RH-14 2E12-F017A (RH 2E51-F080 (RH) 888 2B RHR Pump

-Remove thermocouples 889 2C RHR Pump Remove thermocouples.

891 LPCS Pump

' Remove extra wiring from C/S 892 2E12-F024B (RH)

Repack valve 896 2DG01K (Administrative) 3.

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

4.

Major changes to Radioactive Waste Treatment Systems.

(None) 5.

Indications of Failed Fuel Elements.

(None)

ZCADTS/7 k

....

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