Text

Monthly Operating Repts for May 1984
	ML20092M904
Person / Time
Site:	LaSalle
Issue date:	05/31/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8407020415
	Download: ML20092M904 (28)
	v • d • e

-

O

,D.

i r

i LASALLE NUCLEAR POWER STATION UNIT 1 t

t MONTHLY PERFORMANCE REPORT MAY 1984 C0t910NWEALTH EDISON CCMPANY I

NRC DOCKET No. 050-373 LICENSE NO. NPF-11 i

I

\\

8407020415 8 kDRADOCK050hhhf3 t

PDR 56 i

Doc m at 0043r/0005r f5

.o TABLE OF CONTENTS F

I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE

- A.

Susanary of Operating Experience B.

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

1.

Amendments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Experiments Requiring NRC Approval 4.

Corrective Maintenance of Safety Related Equipment C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System l

l

[

l l

l l'

I i

i i

l i

i l

~

t Document 0043r/0005r

~

I.

INTRODUCTION i

The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marseilles, Illinois.

Each Unit is a Boiling.

Water Reactor with a. designed electrical output of 1078 i

NWe net. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. Unit One is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982. The unit commenced commercial generation of power on January 1, 1984. Unit Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was t

March 1G, 1984. The Unit is expected to commence commercial generation of power in August,

'84.

This report was complied by Randy S. Dus telephone f

number (815)357-6761, extension 324.

i i

o w

y,--

,yw.-.,

-,, - --,e-- - - -, ---

o 8

II.

MONTHLY REPORT FOR UNIT ONE I

A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE L

May 1-31 The Unit started the reporting period at 97%

power with the main generator on line. At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on May 6, reactor power was reduced to 68% for a rod sequence change. At 0000 hours0 days 0 hours 0 weeks 0 months on May 8, reactor power was r ised to 81%. At 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months on May 9, reactor power was raised to 95%. At 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months on May 13, commenced load drop to 94% from 98% for turbine bypass valve testing. At 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on May 14, reactor power was again raised to 98%. At 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months on May 27, reactor power was reduced to 46% due to a TDRFP trip.

At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on May 27, reactor power was raised to

.63%.

At 0000 hours0 days 0 hours 0 weeks 0 months on May 28, reactor power was raised to 75%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on May 28, reactor power was raised to 86%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on May 29, reactor power was raised to 93%. At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months on May 31, the main l

turbine tripped due to a loss of condenser vacuum and a reactor scram followed. The reactor was critical for

[

736 hours0.00852 days 0.204 hours 0.00122 weeks 2.80048e-4 months and 20 minutes.

i l

l l

i l

l l

Document 0043r/0005r

I s

B.

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

1.

Amendments to facility license or Technical Specification.

There were no amendments to the facility license or Technical Specification.

r 2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring WRC l

approval.

3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval.

l l_

4.

Corrective maintenance of safety related equipment.

l The following table (Table 1) presents a summary of safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include: Work Request numbers, LER aumbers, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

i l

LTP-300-7.

TABLE 1

.R;vicion'3 CORRECTIVE MAINTENANCE OF-'

March 1, 1983 5

SAFETY RELATED EQUIPMENT I

I I

I l

4 WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS

. CORRECTIVE ACTION ON SAFE OPERATION I

I I

L22394 RHR Press.

Would not pass adequate lacrease steam condensing Modified press. control control VLV supply of steam to Ht.

time valve.

L24416 Drywell shield Not installed, leaving Additional heat input to-Installed shield wall wall doors openings in sacrifical.

drywell.

doors.

shield.

L29821 Diesel Gen-Undersized wiring causing D/G trip with concurrent Replaced temporary erator con-excess burden on current loss of offsite power and wiring with perma-trol circuit trans.

ECCS initiation.

nent fix.

L35404 Cable Tray Debris found in cable Potential Fire hazard Cleaned cable tray.

. tray.

I L35815 SBGT Rad Particulate channel does Unknown particulate count Replaced defective Monitor not respond to source.

components and recalibrated.

l 2

L36671 Diesel Gen-Low oil level in DAG-Potential loss of speed Fill oil reservoir.

erator Governor Reservoir, control.

L37111 ADS Valve Low Accumulator pressure Adequate pressure still Recalibrated pressure pressure alarm up available.

switch.

i i

I m..

P i

i h

C.

LICENSEE EVENT REPORTS

~

The following is a tabular susmary of all licensee event reports for I

S LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, May 1 through May 31. 1984. This information is provided l

i pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

5 Licensee Event Report Number Title of Occurrence Date i

84-022-00 4/14/84 Reactor Scram on Low RPV level l

84-023-00 4/15/84 Reactor Water Clean up System f

PCIS Isolation on High

. Differential Flow.

i 84-024-00 5/2/84 Electrical Cable Penetrations Inoperable.

i

+

b l

E o

h

r s.

e 1

l D.

DATA TABULATIONS The following data tabulations are presented in this report:

i i

1.

Operating Data Report P

t

~2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions O

i a

b L'

LTP-300-7 Rsvisicn 3 4

March 1, 1983 7

1.

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE June 5. 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD:May 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078 3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 736.3 2594.4 2594.4

_6.

REACTOR RESERVE SHUTDOWN HOURS 7.7 1019.7 1019.7 7.

HO' IRS GENERATOR ON LINE 736.3 2456.6 2456.6 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2120699 6767940 6767940 10.

GROSS ELEC. ENERGY GENERATED (MWH) 777907 2229872 2229872 11.

NET ELEC. ENERGY GENERATED (MWH) 750769 2119305 2119305 12.

REACTOR SERVICE FACTOR 99.0%

71.1%

71.6%

13.

REACTOR AVAILABILITY FACTOR 100%

99.1%

99.8%

14.

UNIT SERVICE FACTOR 99.0%

67.3%

67.8%

15.

UNIT AVAILABILITY FACTOR 99.0%

67.3%

67.8%

16.

UNIT CAPACITY FACTOR (USING MDC) 97.4%

56.1%

56.5%

17.

UNIT CAPACITY FACTOR (USING DESICN MWe) 93.6%

53.9%

54.3%

18.

UNIT FORCED OUTAGE RATE 1.0%

27.4%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

On October 1, 1984 there will be a four week outage to inspect the drywell and perform scheduled surveillances.

j 20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: June 3.

1984 21.

UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COMMERCIAL OPERATION 1/1/84 l

LTP-300-7 RIvlsten 3 March 1, 1983 6

2. AVERAGE DAILY UNIT POWER LEV 1 DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: JUNE 5. 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 NONTH: May 1984 DAY AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL (NWe-Net)

(NWe-Net) 1.

1083 1

1081 2.

1085 18.

1089 3

1076 19.

1079 4,

1073 20.

976 5.

1059 21.

1058 6.

669 22.

1065

'7.

745 23.

1067 8.

941 24.

1065 9.

1064 25.

1068 10.

1085 26.

-1065 11.

1090 27.

588 12.

1068 28.

886 13.

1081 29.

1031 14.

1065 30.

1080 15.

1089 31.

721 16.

1093 INSTRUCTIONS On this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there msy be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

l

LTP-3OO-7 LRevici 2 3 March 1, 1983 19.. (Final) 3.

UNIT SHUTDOWNS AND POWER-REDUCTIONS DOCKET NO., 050-374 UNIT NAME LaSalle One DATE June 5. 1984 REPORT MONTH MAY 1984 COMPLETED BY Randy S.-Dus TELEPHONE (815)357-6761 4

t..

METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS / COMMENTS 9

5/31/84 F

7.7 A

3 Loss of condenser vacuum as a result of blown SJAE & S.P.E. Loop Seals. Resulted in Turbine trip & Reactor scram. Procedure revisions in progress to ensure loop seals remalo filled.

1 i

l DOCUMENT OO44r/OOO5r

i E.

UNIQUE REPORTING REQUIRIDIENTS L

1.

Safety / Relief valve operations for Unit one.

There were no relief valve operations for Unit one for this i

reporting period.

4..

s i

5 l

e

,------w--,

=%.,_

y

--ew.-

--e#-

y--r-,-wa-

-,-e

-e p

e----r-

f s,

2.

D?CS Systems Outagso' u.

i Th~eifollowing outes;,es=were takaa on-ECCS Systema during the repoiting perico.

OUTAGE NO.

EOUIFNN_T,. --..

PURPO:12 OF OUTACL s

.. x s

1-430-84

'l D/G Lubelcation'

~'

.s.

1-438-84%

LPCU W/L Pump

. Repair 011' Bubbler

}

\\{lhCSPumpBreaker.

Inspect Breaker Switch.

~~ '

1-442-84'?.g -

t

_x.

Off-Si'te Dose Calcul, ati,,6n Manual

~#

,T-3.

+~

la,

r,

~

There met so changes to the off-site dose calculat[ ions manual

. duri'ng'this, reporting period.

w 4.~ Radioactive Weste Treatment Systems.

t,.

.{ m There. pre no changes to the Radioactive Wahte, Treatment System

'duchi this reporting period.'

\\

t G

,N e-s~

s g

x s

ij s ', 7,~i y

~,s.,

N ! ;i(

_l 3

i-s

.

pg c s ' s-y y

.,,m

.J

}'L V\\ ~ (.

\\,

s

q..

4 g

i.

g si s

tg

\\l > 'i l _

(g y

T s.

i g%

s jt.

ij i

r i-

n v.

8t y

w l

N

\\s s

A s

,s s

..;ix

,?

r

..[

h l.

y p

(

.s S

n,.

g, g

,'\\

\\

p'

.\\-

G

\\' -

\\

t s,

'N

,i s;,'

s s

\\* ' %

\\

.' N u -

s t

s w

1 s

,,4 g

w

,A

\\,

i, is '

s i,.

s, i

't

\\-

ny

~

. n., v 3.-

t Documett 3r/0005r q

t 4

LASALLE NUCLEAR POWER STATION U?flT 2 MONTHLY PERFORMANCE REPORT MAY 1984 i.

\\

C0tet0NWEALTH EDISON COMPANY l

l l

l NRC DOCKET NO. 050-374 i.

1 LICENSE NO. NPF-18 i

h-

-Document 0043r/0005r u_.

j

a..

/

TAILE OF CONTENTS 4

I.

INTRODUCTION II.

NOKIHLY IGPCRT FCE UNIT IWO

,;s y A.

Susumary of Up.'srating E4velence l

B.

PLANT O

F. PROCEDURE

~ CHANGES;. TESTS, EXPERIMENTS, AND l

SAFETY REI.ATED MAINTENANCE f

i t

..1 il'.

Amendniectr.to Facility License or Technical s

f, Specifiest:lons

-' I.'

Facilityfor Procedura Changes Requiring NRC Approval -

'.'3.

Tests and Esperiments Requi?ing kRC Approval I

J 4.

Coerective Maintenance of Safety kelated

. Equipment s

r 3

C.

LICENSEE EVEhr EEPORTSE J-

,D.

tDATA TABULATICNS v

1.'. - Operat8.aff y Data Report -,

7l./

-? 3.gAveragr4 Deily, Unit 1 Power Level Uni,t~ Shutdowns and ' Power Reductions l

c r

'E.,

UNIQUE REPORTING'REQUIEDIENTS

/

,1.

Safety / Relief Valve 0perationsj x

i'.

'2.

ECCS Syste'A 02 tag es -

3.

Off-Site. Dose, Calculation Manual Changes-

~ '

~ 4, Rajor Changtes to, Radioactive Waste Treatment

~

System

- S

~ -

h r

j

.F,

e:

1 T

i

)

~,

~

q:y ~.

.)

,j.

[

d h

O' "l 1

~

l i

i l,

i-a' A

2 J

A w

l

{.

e a

~

l I.

INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marseilles, Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The station is owned by commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.

i The condenser cooling method is a closed cycle cooling pond. - Unit One is subject to License Number NPF-11, I

issued on April 17, 1982. The date of initial criticality was June 21, 1982. The unit commenced commercial generation of power on January 1, 1984. Unit l

Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984. The Unit is expected to commence commercial generation of power in August, '84.

l This report was complied by Randy S. Dus, telephone number (815)357-6761, extension 324.

a 6

1 i

h Document 0043r/0005r

i

- II.

MONTHLY REPORT FOR UNIT TWO i

i A.

SUISIARY OF OPERATING EXPERIENCE FOR UNIT TWO i

May 1-5 The unit started the reporting period at 21%

[

power with the main generator on line. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on May 2, the main turbine was tripped during surveillance LOS-TC-W1.

At 0515 hours0.00596 days 0.143 hours 8.515212e-4 weeks 1.959575e-4 months on May 2, the main turbine was back on line. At 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months on May 3 the turbine was again tripped during startup testing. At 2135 hours0.0247 days 0.593 hours 0.00353 weeks 8.123675e-4 months on May 3, commenced normal unit shutdown to hot standby for maintenance work. At 2340 hours0.0271 days 0.65 hours 0.00387 weeks 8.9037e-4 months on May 3, the reactor

-was manually scrammed due to reactor water level transients. The reactor was critical for 71 hours8.217593e-4 days 0.0197 hours 1.173942e-4 weeks 2.70155e-5 months and 40 minutes.

Hay 6-21 The reactor went critical at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on May 6.

At 0506 hours0.00586 days 0.141 hours 8.366402e-4 weeks 1.92533e-4 months on May 8 the main generator was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on May 8, reactor power was raised to 21%. At 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months on May i

11, commenced normal reactor shutdown for turbine

~

maintenance. At 0102 hours0.00118 days 0.0283 hours 1.686508e-4 weeks 3.8811e-5 months on May 12, the main turbine was manually tripped. At 1640 hours0.019 days 0.456 hours 0.00271 weeks 6.2402e-4 months on May 12, the l

reactor was placed back in "run" mode. At 1723 hours0.0199 days 0.479 hours 0.00285 weeks 6.556015e-4 months on l

May 12, the main generator was synchronized to the grid. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on May 12, reactor power was raised to 24%. At.1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months on May 17, the main turbine was

-tripped for STP 27-2.

At 1625 hours0.0188 days 0.451 hours 0.00269 weeks 6.183125e-4 months on May 17, the main generator was synchronized to the grid. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on May 19, reactor power was raised to 34%. At 1825 I

hours on May 21, the main turbine tripped with a subsequent reactor scram. The reactor was critical for 361 hour0.00418 days 0.1 hours 5.968915e-4 weeks 1.373605e-4 months s-and 25 minutes.

May 22-24 The reactor went critical at 2258 hours0.0261 days 0.627 hours 0.00373 weeks 8.59169e-4 months on i

.May 22.

At 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months on May 22 commenced reactor shutdown. At 0301 hours0.00348 days 0.0836 hours 4.976852e-4 weeks 1.145305e-4 months on May 23, the made switch was taken to " Shutdown". The. reactor was critical for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 3 minutes.

May 25-31 The reactor went-critical at 1625 hours0.0188 days 0.451 hours 0.00269 weeks 6.183125e-4 months on i

May 25.

At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months on May 26, the main generator was synchronized to the grid. At 1954 hours0.0226 days 0.543 hours 0.00323 weeks 7.43497e-4 months on May 26, the

i. -

main turbine tripped on high level in the NSR.

At 2026 hours0.0234 days 0.563 hours 0.00335 weeks 7.70893e-4 months on May 26 the main turbine was synchronized to the grid. At 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months on May 27, commenced reactor

= shutdown to repa*e the number 3 bypass valve. At 0738 j

hours on May 27, the main turbine was tripped. At 1500 j

hours on May 27, commenced startup fece hot standby to I

power operation. At 2240 hours0.0259 days 0.622 hours 0.0037 weeks 8.5232e-4 months on May 27, the reactor mode switch was taken to run and the reactor power level was 6%.

At 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months on May 28, the main generator was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on May 28, reactor-power was raised to 24%. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on May 28, reactor power was raised to 44%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on-May 29, reactor power was at 25%. The Unit completed the reporting period at 26% power. The reactor was critical for 151 hours0.00175 days 0.0419 hours 2.496693e-4 weeks 5.74555e-5 months and 35 minutes.

rm v:c ~ W u im W g R w a

I l

i

'D.

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

i i

1.

Amendments to facility license or Technical Specifications.

There were no amendments to the facility license or Technical Specifications during the reporting period.

t 2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC approval during'the reporting period.

3.

Tests and experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during

.the' reporting period.

l 4.

Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a sumanary of l

safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary I

. include: Work Request numbers, LER Numbers, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

i U

LTP-30017 iTABLE 1.

Ravicic2 3 Marsh 1,,1983 CORRECTIVE MAINTENANCE OF-5 SAFETY RELATED. EQUIPMENT I

I I

WORK REQUEST LER COMPONENT.

.CAUSE OF MALFUNCTION-

'RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

I 1

I I

L35686 Mainsteam line Indicating needle bent Inaccurate ESL OPI reading Straigat.ined needle and' D/P Gauge rec'alibrated.

L36018 Ex Bldg B PRM PRM is reading decade-None. Redundant channels Replaced GM Tube and above other detectors still operable, recalibrated.

L36066 Ammonia-Broken power' lead to Causes spurious alarm Repaired faulty lead detector

. alarm relay.

L36367 Rx Blds to Both doors open at same Potential loss of secondary Repaired interlock Aux Bldg.

time containment Air lock

&O2 concen-Recalibrated post i

L36438 Div I Post Instrumentation Drift Unknown H2 Loca monitor trations during Loca Loca monitor.

L36504 Drywell Interlock mechanism Door sticks, potential Adjusted Linkage Airlock

-sticks

' personnel. safety.

L36888 84-018-00 HPCS Pump'

.HPCS Breaker did not Unable to start HPCS. pump Replaced faulty con-bekr.

close on attempt to

tacts, start pump.

DOCUMENT 0044r/0005r

s..

C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Lasalle Nuclear Power Station, Unit Two, occurring during the reporting period, May.'1 through May 31, 1984.

.This information is provided

[

i pursuant to the reportable occurrence reporting requirements as set forth

'in 10CFR 50.73.-

. Licensee Event Report Number Date Title of Occurrence I

'84-012-00 4/26/84 Reactor Manual scram due to L

loss of normal feedwater.

34-013-00 4/3/84 Reactor Water clean up Differential pressure isolation. 014-00 4/3/84

-High Pressure core spray jockey pump failure, r-84-015 4/11/84 Failure to realize limiting condition of operation prior to changing mode.

84-016-00 4/23/84 Reactor water clean up high ambient temperature isolation.

~84-017-00 S/3/84 Reactor scrac on loss of.

feedwater.

t m

l l

l-t I

L 6

O.

D.-

DATA TABULATIONS The following data tabulations are presented in this report:

1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

-Unit Shutdowns and Power Reductions 6

LTP-300-7 Revision 3 March 1, 1983 7

1. OPERATING DATA REPORT DOCKET NO. 050--374 UNIT LaSalle Two DATE June 5. 1984 COMPLETED BY gas R. Lintakas TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: May 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (IWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078 3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A

- 4.

REASONS FOR RESTRICTION (IF ANY):

THIS EONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 588.7 1296.8 1296.8 6.

REACTOR RESERVE SHU MWN HOURS 155.3 686.0 686.0 7.

HOURS GENERATOR ON LINE 473.7 581.1 581.1 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 t

9.

GROSS THEREAL ENERGY GENERATED (MWH) 444715 596465 596465 10.

GROSS ELEC. ENERGY GENERATED (MWH) 110201 126884 126884 11.

NET ELEC. ENERGY GENERATED (MWH) 98877 113093 113093 12.

REACTOR SERVICE FACTOR N/A h/A N/A 13.

REACTOR AVAILABILITY FACTOR N/A N/A N/A 14.

UNIT SERVICE FACTOR N/A N/A N/A 15.

UNIT AVAILABILITY FACTOR N/A N/A N/A 16.

UNIT CAPACITY FACTOR (USING MDC)

N/A N/A N/A 17.

UNIT CAPACITY FACTOR (USING DESIGN MWe)

N/A N/A N/A 18.

UNIT FORCED OUTAGE RATE N/A N/A N/A i

19.

SHUTDOWNS SCHEDULED OVER NEIT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH) 20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

N/A 21.

UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED l

INITIAL CRITICALITY 3/10/84 l

INITIAL ELECTRICITY 4/20/84 j.

COMMERCIAL OPERATION Aug. 84 i

I l

l

,y-

_-,y-,..----_yr

-s, y

LTP'300-7 Rnvisica 3 March 1, 1983 6

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: June 5. 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 NONTH: May 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(NWe-Net) 1.

166 17.

212 2.

171 18.

205

.3 76 19, 302 4.

0 20.

295 5.

0 21.

236 6.

0 22.

0 7.

0 23.

0 8.

135 24.

0 9.

152 25.

0 10.

169 26.

23 11.

168 27.

35 12.

48 28.

291 13.

176 29.

292 14.

176 30.

195 15.

182 31.

178 16.

239 INSTRUCTIONS' On this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

6

LTP-300-7' Rev.ision 3 March 1, 1983-9 (Final)

ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374' UNIT NAME LaSalle Two DATE June 5, 1984 REPORT. MONTH. MAY 1984-COMPLETED BY Randr S.

Dus TELEPHONE (815)357-6761-METHOD OF

' TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS / COMMENTS 9

5/2/84 S

.3 B

9 Turbine Trip during Startup Testing 10 5/3/84 S

114.6 B.

2 Performed Minor Maintenance work 11 5/12/84 S

16.4 B

9 Turbine trip during Startup testing 12 5/17/84 S

.7 8

9 Turbine Trip during Startup testing 13 5/21/84 F

120.6 A

3 Reactor Scram Following Turbine trip from main transformer l

differential current relay trip.

DOCUMENT 0044r/0005r

_ _ =,

s LTP-300-7.'

=-

Revicion'3

. March 1, 1983 9 (Final)

. ATTACHMENT E 3.'. UNIT SHUTDOWNS AND POWER' REDUCTIONS

. DOCERT NO. 050-374 t

- UNIT NAME LaSalle Two DATE June 5. 1984 REPORT MONTH.MAY' 1984 COMPLETED BY Randy S.-Dus TELEPHONE (815)357-6761 METHOD OF-TYPE SHUTTING DOWN F: FORCED DURATION THE RFACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS / COMMENTS 14 5/26/84 F

.5 A

9 Turbine trip on MSR high level 15' 5/27/84 S

17.3' B

9 Turbine trip to

~

perform maintenance on #3 bypass valve.

I DOCUMENT OO44r/0005r

~.

. i.

o-l E..

UNIQUE REPORTING REQUIRENENTS I

?

4 r

k 1.

Safety / Relief Valve Operations for Unit Two.

.There were no relief valve operations for Unit Two for this reporting period.

i t

t

[

i I

r

-f h

I

~f i

i i

i I

f GWr~rAJMNWaimi2r>

..,.. - ~ - - - -.

.o 2.

ECCS Systems Outeges The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 2-649-84 Bus 243 HPCS Pump Breaker Testing 2-655-84 South ADS Bottle Repair Leak Bank Pressure Indicator 2-688-84 HPCS W/L Pump Lubricate Coupling 2-689-84 LPCS W/L Pump Lubricate Coupling 3.

Off-Site Dose Calculation Manual There were no changes to the off-site dose calculations manual during this reporting period.

4.

Radioactive Waste Treatment Systems.

There were no changes to the Radioactive Waste Treatment System during this reporting period.

1

Commonwedith Ethon N

LaSilla County Nucle r Station Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 June 5, 1984 Director Office of Management Information and Program Control United States Nuclear Regulatory Commission 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 the period covering May 1 through May 31, 1984.

Very truly yours, i

G J. Diederich Superintendent LaSalle County Station GJD/RSD/cch Enclosure 1

xc:

J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle I

Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Ferrar CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident if Document 0043r/0005r

-

ML20092M904

Text

SUMMARY

F. PROCEDURE

Navigation menu

Search