Text

Monthly Operating Repts for Apr 1984
	ML20091K481
Person / Time
Site:	LaSalle
Issue date:	04/30/1984
From:	Diederich G, Lintakas A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8406070100
	Download: ML20091K481 (32)
	v • d • e

, . .

.e i

e i

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT APRIL 1984 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

l l

l 8406070100 840430 l PDR ADOCK 05000373 t R PDR

t TABLE @F CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE A. Summary of Operating Experience ,

B. PLANT O

R. PROCEDURE

CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

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 REPORTINC REQUIRENFJITS

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 i

t

..~

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 set. 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 nothod is a closed cycle cooling pond. Unit One is subject to License Numbcr 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 NFP-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984. The Unit is expected to commence coasmercial generation of power in August, '84.

This report was compiled by Aras R. Lintakas telephone number (815)357-6761, extension 324.

I l

l

II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE Apell 1-14 The unit started the reporting period at 95%

power with the generator synchronized to the grid. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on April 2. Leactor power was lowered to 75%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on April 4, reactor power was raised to 97%. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months on April 7. Reactor power was reduced to 75%. At 0710 on Apell 10, Reactor Power was raised to 97%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months , reactor power was lowered to 52%. On April 14 at 1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months , the reactor scrammed on low reactor water level. This was due to feedwater transients during testing of the "B" turbine driven reactor feedwater pump after maintenance. The reactor was critical for 331 hours0.00383 days 0.0919 hours 5.472884e-4 weeks 1.259455e-4 months and 5 minutes.

April 15-30 The Reactor went critical at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on April 15. On April 16 at 0525 hours0.00608 days 0.146 hours 8.680556e-4 weeks 1.997625e-4 months , the turbine hts i synchronized to the Grid. At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months on April 16, Power was increased to 291. At 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months on April 16, l

Reactor power was increased to 53%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months , l

reactor power was increased to 81%. On April 21 at l 0320, reactor power was increased to 97%. The reactor was critrical for 369 hours0.00427 days 0.103 hours 6.10119e-4 weeks 1.404045e-4 months and 30 minutes.

l i

1 t

l I

l l

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

1. Amendments to facility license or Technical Specification.

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

2. Facility or procedure changes requiring NEC approval.

'There were no facility or procedure changes requiring NRC approval.

3. Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval.

4. Corrective maintenance of safety related equipment.

The following table (Table 1) presents a sumanary of

! 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.

l l

Cause of Malfuaction, Results and Effects on Safe Operation, and i

l Corrective Action.

I I

l l

i

LTP-300-7 - -

TABLE l- R'visico

3 March 1, 1983 .

1 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT I

I l I I I COMPONENT CAUSE OF NALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION WORK REQUEST LER ON SAFE OPERATION l ~

I I I l I

35477 SBGT WRGN Broken BNC Connector on Inaccurate indication on Resoldered wire to Low Range Selector low range connector and tightened in place.

A" VE Coupling failure Compressor inoperable. Reassembled coupling 35616 Verified operation.

compressor OVE04CA Incorrect wiring Correct dampers will not Corrected wiring and 34947 84-021 OKY125B isolate on high ammonia checked for proper Ammonia detection. contact operation.

detector.

1D18-K609D Relay Board Damaged "D" VR Rad Monitor in Replaced relay board 34929 84-020 VR RAD monitor tripped condition 34607 84-019 IE31-R620 Spurious failure of Inaccurate indication on Calibrated per RWCU leak summer card diff, flow meter. LIS-RT-101 detection 34107 84-018 Various NCC's Butt splice inspection Inspection to verify correct Inspection per-work performed. formed by E.M.

Dept. QC & QA.

Verification &

Document Review.

OVE03CB Abnormal wear of fan None "A" train still Replaced fan and 30858 and motor. operable, motor.

1 OD18-N512 Bad Mid & High Range SBCT No SBGT Wide Range Gas Replaced with new 35285 j

OD18-N513 Cas monitor detectors monitor indication detectors recal-ibrated per LCP-820-24 l

35364 OPI-VC134 Dirty oil screen. Compressor OVC05CA trips on Cleaned oil screen l low oil pressure.

Compress or trips.

DOCUMENT 0044r/0005r I -

rs,

e I

l -

C. LICENSEE EVENT REPORTS l

The following is a tabular susunary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, April 1 through April 30, 1984. This information is provided

pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 84-018-00 3/10/84 control Cable Butt Splice failure.

84-019-00 3/20/84 RWCU Differential flow transitter out of calibration.

84-020-00 3/27/84 Group IV PCIS isolation 84-021-00 3/27/84 Control Room HVAC System Asumonia Detector IMOP.

i 1

4

- _ . ,- _ _ . , . , . . - - _ _ . _ _ . , , _ _ _ , _ , . . __ _,y-,,____, , _,_, _ . _ _ , _ _ _ . __ _ _ _ _ _ _ , __, . , , . _, _ ... _ _,_ 7_,._,_, __ ,

l ..

I D. DATA TABULATIOlls The following data tabulations are presented in this report:

1. Operating Data Repoet

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions

t

- LTP-300-7

'. Envisics 3 March 1, 1983 7

1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE Apell 15. 1984 COMPLETED BY Aras R. Lintakas TELEPHONE (815)357-6761, OPERATING STATUS

1. REPORTING PERIOD: April 1984 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (Infe-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 699.6 1858.1 1858.1

6. REACTOR RESERVE SHUTDOWN HOURS 19.4 1012.0 1_012.0

7. HOURS GENERATOR ON LINE 684.7 1720.3 1720.3

8. UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2065440 4447241 4447241

10. GROSS ELEC. ENERGY GENERATED (MWH) 692699 1451965 1451965

11. NET ELEC. ENERGY GENERATED (MWH) 663674 1368536 1368536

12. REACTOR SERVICE FACTOR 97.3% 64.0% 64.0%

13. REACTOR AVAILABILITY FACTOR 100% 98.9% 98.9%

14. UNIT SERVICE FACTOR 95.2% 59.3% 59.3%

15. UNIT AVAILABILITY FACTOR 95.2% 59.3% 59.3%

16. UNIT CAPACITY FACTOR (USING MDC) 89.1% 45.5% 45.5% l

17. UNIT CAPACITT FACTOR (USING DESIGN j MWe) 85.6% 43.7% 43.7%

18. UNIT FORCED OUTAGE RATE 4.8% 34.8% 34.8%

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

SEPTEMBER 1984, TWO WEEK SHUTDOWN FOR SCHEDULED SURVEILLANCES.

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 INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 C099tERCIAL OPERATION 1/1/84

, l l

l 1

l j

1 LTP-300-7 l s,

- - R:visies 3 March 1, 1983 6

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373

- UNIT: LASALLE ONE DATE: APRIL 15. 1984 COMPLETED BY: Arts R. Lintakas TELEPHONE: (815) 357-6761 HONTH: April 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (NWe-Net)

1. 967 17. 732

2. 848 18. 818 3 969 19. 876

4. 1039 20, 1027

5. 1077 21. 1041

6. 1085 22. 949

7. 813 23. 1063

8. 897 24. 1082

9. 1035 25, 1075

10. 1070 26. 1056

11. 1077 27, 1064 i

l

12. 1078 28, 1057 i 13. 1073 29. 978 l

l 14. 475 30, 1071 l

15. 0 31. N/A l

l

16. 319 i

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

l These figures will be used to plot a graph for each reporting month. Note l that when maximum dependable capacity is used for the net electrical rating of j the unit there may be occasions when the daily average power level exceeds the l

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 enomaly.

l l

LTP-3OO-7 '

RsvisicQ 3 -

March 1, 1983 9 (Final)

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE May 10, 1984 REPORT MONTH APRIL 1984 COMPLETED BY Aras R. Lintakas CONTINUED 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 8 4/14/84 F 34.3 G(1) 3 Procedures were changed to more clearly define the operational setpoints (1) The operator changed the setpoint of the reactor water level control below the operational level. allowed by existing peccadures for paralleling an additional feedwater pump. This resulted in a low reactor water level scram.

DOCUMENT 0044r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit 1.

There were no relief valve operations for Unit one for this

j. reporting period.

l i

l l

t l

{

. . 2. ECCS Systems Outagsa The following outages were taken on ECCS Systems during

. the reporting period.

OMTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 1-363-84 S/D Cooling Suction Prevent S/D Cooling Initiation w/ vents open.

1-381-84 IB D/G Air Comp. Design evaluation 1-395-84 1A D/G Inspect oil pump & strainer.

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.

o I

l I

l l

I i

l l

{

t

t .

l.

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT I

APRIL 1984 I

COIGIONWEALTH EDISON COMPANY g

', NRC DOCKET No. 050-374 LICENSE NO. NPF-18 l

I l

l l

l I

t

TABLE CF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. PLANT OR PROCEDUEE CHANCES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

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. Safety / Relief Valve Operations

2. ECCS System Outeges

3. Off-Sito Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - 1

I. INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marsellies, Illinois. Each Unit is a Bolling Water Reactor with a designed electrical output of 1078 INe net. The Station is owned by Coasmonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Coasnonwealth 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 March 10, 1984. The Unit is expected to coassence coasnercial generation of power in August, '84.

This report was compiled by Aras R. Lintakas, telephone number (815)357-6761, extension 324.

l 1

I e.

i i

!~ II. MONTHLY REPORT FOR UNIT TWO A. SUIglARY OF OPERATING EXPERIENCs FOR UNIT TWO April 1-2 The Unit started the reporting period with the reactor critical at less than 1% power. At 0125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months on April 2, the reactor was shutdown. The reactor was critical for 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months and 25 minutes.

April 2-14 The reactor went critical at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on April 2. At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on April 14, the reactor was shutdown. The reactor was critical for 320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months and 0 minutes, i April 18-26 The reactor went critical at 0437 hours0.00506 days 0.121 hours 7.225529e-4 weeks 1.662785e-4 months on Apell 18. The generator was synchronized to the grid at 1809 hours0.0209 days 0.503 hours 0.00299 weeks 6.883245e-4 months on Apell 20. At 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months on April 20, the generator was removed from the grid. At 2050 hours0.0237 days 0.569 hours 0.00339 weeks 7.80025e-4 months on April 20, the generator was synchronized to the grid.

At 2113 hours0.0245 days 0.587 hours 0.00349 weeks 8.039965e-4 months on April 20, the generator was removed from the grid for lockout verification. At 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on April 21, the generator was synchronized to the grid. At 1740 hours0.0201 days 0.483 hours 0.00288 weeks 6.6207e-4 months on April 21, the generator was removed from the grid. At 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months on April 22, the generator was synchronized to the grid. On April 22 at

1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months , the generator was removed from the grid for testing. At 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months on April 22, the generator was synchronized to the grid. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on April 24, Reactor power was increased to 18%. At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months on Apell 25 the generator was removed from the grid. On April 26 at 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months , the reactor was manually scrammed due to problems with condensate suction strainers. The reactor was critical for 192 hours0.00222 days 0.0533 hours 3.174603e-4 weeks 7.3056e-5 months and 28 minutes.

April 28-30 The reactor went critical at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months on April 28. At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months on Apell 29, the generator was synchronized to the grid. AT 2147 hours0.0248 days 0.596 hours 0.00355 weeks 8.169335e-4 months on Apell 29, the generator was removed from the grid. On Apell 30 at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months , the generator was synchronized to the grid.

At 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months on Apell 30, reactor power wa6 at 18%.

?

The reactc; was critical for 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months and 45 minutes.

i i

1

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY REI.ATED MAINTENANCE.

1. Asunendments to facility license or Technical Specifications.

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

2. Facility or procedure changes requiring Nec approval.

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

3. Tests and esperiments requiring NRC approval.

The abstract to the residual heat removal system startup test, table 14.2-134, was revised. This was approved by telephone conversation with Mr. Richard Becker on Apell 16, 1984. (See Attached.)

4

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a susunary of safety-related maintenance completed on Unit one during the reporting period.

The headings indicated in this susumary include: Work Request numbers, LER Numbers, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

, ., . ,.-..,,.,,.,,,-- _ v- m.,,__ ,,_. e , _ , , _ _ , ,- , . _ , ,. --.,-

n ______.,,._n,_

6

.4 ,,'[ '

p 'l ,

l

, /[s . April 17, 1984 TO: ' A. Bournia ',

n

SUBJECT:

Commonwealth Edison Cdapany

LaSalle County Stadon

.., FSAR Changes Relating to the Startup Test Program i! v.

3- ,

REFERENCE:

Telephone Conversat.fon with~Mr. Richard Becker

, 05 April 16, 1984. -

. \ r>

! t J.,'

[,.

jU

. (

Per ouratelephone, Conversation *'with Dick on April 16, 1984 we are it inforaally transmittiis the enclosed marked up changes to the LaSalle County Station FSAR6: Please forward these changes to Dick for his use.

> j 1 1

g3 These pe ticipating in the referenced tel.ephone conversation included Robert Bishop, . Ada:Inistrate Assistant Svperintendent - LaSalle Station and Mr. .

William Guldemond, Senior Resident Insph tor fer LaSalle - WRC Region III .

These changes will be included in the next revision to the FSAR and have been

}J' i tentatively agreed upon per this' telephone conversation.

Please feel free to call if you J have any(impediate problems with the

!' proposed changes. When your revies has been cEnoleted, a conference call to

! confirm their acceptability isl requested so that<a formal change to the

! LaSalle County Station FSAR can' be submitted.

y' d j

/

s, n . ,

(

,~ f ,

( t G. J. Diederich

,4, 9 ,

' ., *- i superintendent t

LaSalle County Station

>" 0 CND/cth I -

y .

- ei '/

/ '

Attachment ,

I i

. CC: J.'C.,Runwick o ;

fp R. D. Bishop. 5 s

l W. Guldemand',5 , , j

! R. Beckar , ;}

'- F, .,

fl l'

,pc. '

): ,

i- . ? ',. ,

~ '

's s' l '

l. ,

l' !,

l

'( ,

DOCUNINT 0218r ,

i lr f) p

e / 9 l . _ - _. - --- - ._ _ 2 _ _ -- ___. . _. -

LSCS-FSAR AMENDMENT 57

, ,, , . ," j JULY 1981 a .

? s TABLE 14.2-134 6;-

a RESIDUAL HEAT REMOVAL !jfl_. CLns. M/" TEST s PURPOSE o_

c The purpose of this test is to demonstrate the ability of h

the Residual Heat Removal (RHR) system to remove residual and decay heat from the nuclear system so that refueling e , and nuclear system servicing can be performed.;nd, - ,:..- renne, ir acr-2 ,,.

,- u---.

-- .: uu uun

- -. - . . - v.-

.. + - e n --

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

i; 1;;1;t;f f ;r I; ; a. ., L; ;;nfe..;; ;t;;; 'hil; _h; ;;;;t; 4 th; 7.cin ::nd ncer.

DESCRIPTION .

=

With h; _;;;t;; ;h: c; 101 p;.:::, I'he condensing mode of the 4 RER system will be tuned.;nf : p;;iti;; f;...;n;t;;-_i. Con-densing heat exchanger performance characteristics will be i

E '

demonstrated. During the fir:t7 suitable reactor cooldown, l

.m the shutdown cooling mode of the RHR system nf the der':n h::t :;r:c;l ::p;bilit; cf th; n:r ::t 2:::hnng; : 111 t:

u r .- =--------s : w ., u d wen e ra cted . m m

- vac4 hw reant capau tY_ ScepteroI o+ s%Poo l coo'$ 4-g ~4E c Kili aL W o % sq 6 :.

[

' Th'e dbcay heat load is insignificant early in the-startup

~

test program. Use of this mode with low core exposure E ~

could result in exceeding the 100* F/hr cooldown rate

& 3-limitation of the vessels if i;th 2:2 h;_t ;nchanscr tre urtc cimult n:: 17 Late in the test program, after accumulating significant core exposure, a suitable demon-O stration can more adecuately,rerify the RHR heat exchangers u

j c pacity, ab.fty E codac u h. see n te.

/ cAc. (c actM., ,

E_ _

g ACCEPTANCE CRITERIA Level 1 F

m Not applicable k .

Level 2 The RHR system shall be capable of operating in the Ct::r-b- '

'ecnf;ncing .:ith betr en 2ni '"c

st "c : "M , suppression pool cooling and shutdown cooling mode (with either heat E exchanger in operation) at the flow rates and t;;.p;;;;;;;but 6A skt E

diff;;;nti;1: indicated on the process diagrams. In the steam E condensing mode, for small disturbancas, each vari bleeted must

= -I have a de' cay ratio less than 0.25 throughout the ex operating range of each controller's expected operatin, range.

{,

m m ,,_ - ,, & # # .e .+ e_

f Co6sq O. -

14.2-280 I

L

.o .LSCS-FSAR AMENDMENT 47 OCTOBER 1979 TABLE 14.2-134 (Con t' d )

T;.m Limc to pi;.;;' th: ?"" '.::t ::: chin ge r ir t'r rtr-~

m e . 2 m . ._ i.., .2d; with th: DCIC .::ing th: h::t c M rP-- cr w..Cm..em-m flew fa ;u; tic. :hc.11 i: 1,': h;ur : 12::. l The RHR system performanca in the shutdown cooling mode shall

.... -m im _ ;hc.c. th:.: ic.fic '-d c .- th: crc:::: di:~r-~ ~

p, orde. x couteo sic.d cooIdom Le3 Shrdowc, INITIAL CONDITIONS

1. All construction tests and preoperational tests are completed and approved.

2. All system instrumentation installed and calibrated.

All systems must be operational as recuired to perform 3.

the test.

m Me Sys> Aco.e ca.dangma., At t ma sc.

Hear tranck o? she froa ss doomm kr tie.

SvPf(c.ssion fool ccolen3 mcdc ,

9 4

14.2-281

LTP-300-7 - - '

TABLE 1 R;visic2 3 -

March 1, 1983 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT I 1. I I I WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I I I I I 34069 ZUR-CM027 Bad AP Cell and circuit Inaccurate Rx level Replaced AP cell &

card Indication. . circuit cart Performed calibration.

30999 RHR Serv. Packing Leak Additional Rx Bldg. Equip. Replaced Packing.

Water Outlet Drain Sump Input Stop 2E12-F068A 34995 RX Level Instr Out of calibration Inaccurate Rx level Recalibrated to in 1B21-NO37D Indication tolerance limits.

35107 "B" Post Loca Erratic Indication No effect on operation Performed LIS-PC-07 02 Monitor 35139 Instr. N2 Foreign material in check Depressurized north ADS Disassembled check Bottle Bank valve seat Bottle bank when IN valve & removed check valve compressor output was low foreign material.

21N043.

35141 IRM "D" Bad 15 VDC Regulator IRM Indicates downscale. Replaced 15 VDC regulator. Performed LIS-NR-02.

35155 2B21-F065A Packing leak Additional Rx Bldg. Equip. Added Packing and 7 rain Sump Input. made adjustments per LMP-CM-01.

35165 Valve 2C11- Valve stuck in open None- Control Rod 34-35 at Removed valve F102 for CRD position. " full in" position, & assembly and 34-35 electrically disarmed. installed plug.

DOCUMENT 0044r/0005r

LTP-300-7 '

TABLE 1 C ::;t'd R;visica 3 ,.

Mirth 1, 1983 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT l l l l l WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I l l l l 35289 HPCS Water Abnormal wear of motor HPCS Inoperable Replaced motor leg pump. bearings.

35334 MSIV limit Limit switch settings Incorrect valve position Adjusted limit switches switches changed due to " Hot" indication. per LES-MS-101.

conditions.

35371 IRM C Detector will not insert None, all other IRM's Readjusted " full out" operable and " full in" limit switches.

35441 2821-F019 Valve will not " seal in" Valve will not fully close Replaced faulty the close direction, torque switch.

35978 2B21-R884A Recorder indicates Incorrect level indication. Performed & recal-wide range upscale, ibrated Per LIS-NB-202 level recorder 35400 2B D/G Leaking fuel oil to None, D/G still operable. Torquod fuel oil stud injector line nut to 40 ft/lbs.

DOCUMENT 0044r/0005r l

C. LICENSEE EVENT REPORTS The following is a tabular sussnary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, occurring during the reporting period, April 1 through Apell 30, 1984. This information is provided pursuant to the reportable occurrence repoeting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

I Licensee Event Report Number Date Title of Occurrence i

l 84-010-00 3/13/84 RWCU Isolation on H16h Pump Room Differential l Temperature.

84-011-00 3/16/84 Reactor vessel Water Level high I switches out of calibration.

l

D. DATA TABULATIONS r

The following data tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns ar.d Power Reductions f

i.

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

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE May 10. 1984 ,

COMPLETED BY Aras R. Lintakas TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: April 1984 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AUTHORIZED POWER LEVEL ( Wt):3323 MAX DEPEND CAPACITY (We-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 583.6 708.1 708.1

6. REACTOR RESERVE SHUTDOW HOURS 135.4 530.7 530.7

7. HOURS GENERATOR ON LINE 107.4 107.4 107.4

8. UNIT RESERVE SHUTDOW HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 143472 151750 151750

10. GROSS ELEC. ENERGY GENERATED (MWH) 16683 16683 16683

11. NET ELEC. ENERGY GENERATED (MWH) 14216 14216 14216

12. REACTOR SERVICE FACTOR N/A N/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

19. SHUTDOWS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

20. IF SHUT DOW AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 3/10/84 INITIAL ELECTRICITY 4/20/84 ColetERCIAL OPERATION Aug. 84

- - :- ;~ w -- -

' ~

LTP-300-7 R;violes 3 March 1, 1983 6

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE T_WO DATE: May 10. 1984 COMPLETED BY: Aras R. Lintakas TELEPHONE: (815) 357-6761 MONTH: April 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (NWe-Net)

1. 0.0 17. 0.0

2. 0.0 18. 0.0 3 0.0 19. 0.0

4. 0.0 20. 0.0

5. 0.0 21. 3

6. 0.0 22. 49

7. 0.0 23. 144

8. 0.0 24. 147

9. 0.0 25. 97

10. 0.0 26. 0

11. 0.0 27. 0

12. 0.0 28._ 0

13. 0.0 29. 49

14. 0.0 30. 137

15. 0.0 31. N/A

16. 0.0 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.

LTP-300-7 Revioica 3 March 1, 1983 : '.

9 (Final)

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle Two DATE May 10, 1984 REPORT MONTH APRIL 1984 COMPLETED BY Aras R. Lintakas TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCIIEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS / COMMENTS 1 4/2/84 S 7.6 B 1 Normal Unit Shutdown.

2 4/14/84 S 83.6 B 1 Normel reactor shutdown to repair motor driven reactor feed pump dis-charge drain line.

Cenerator was synchronized to the grid for the first time on April 20, 1984 at 1809 hours0.0209 days 0.503 hours 0.00299 weeks 6.883245e-4 months .

3 4/20/84 F 2.5 A 1 Instrumentation repaired 4 4/20/84 S 20.3 B 1 Verification of Generator Lockout.

5 4/71/84 F 17.1 A 1 High vibration on bearing

5.

6 4/22/84 S .8 B 1 Overspeed testing.

DOCUMENT 0044r/0005r i

~

LTP-300-7 .

R; vision 3' ..

March 1, 1983 ,-

9 (Final)

3. UNIT SHUTDOWNS AND POWER REDUCTIONS (CONT'D)

DOCKET NO. 050-373 UNIT NAME LaSalle Two DATE May 10. 1984 REPORT MONTH APRIL 1984 COMPLETED BY Aras R. Lintakas CONTINUED TELEPHONE (815)357-6761

(

METHOD OF 4

TYPE SHUTTING DOWN 1

F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS /COI9fENTS

7 4/25/84 F 91.1 A 1 Defective Generator thrust BearinE thermocouple 4;

8 4/29/84 6.7 A 1 Leak in EHC #1 control valve fixed.

)

i l

i i

l i

I DOCUMENT 0044r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit 2.

VALVES - NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATIONS CONDITION OF EVENT 4/11/84 2B21-F013A 5 Manual 902 PSIG LST 83-350 4/11/84 2B21-F013B 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013C 4 Manual 902 PSIG LST 83-350 4/11/84 2B21-F013D 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013E 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013F 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013G 4 Manual 902 PSIC LST 83-350 4/11/84 2B21-F013H 4 Manual 902 PSIG LST 83-450 4/11/84 2B21-F013J 4 Manual 902 PSIC LST 83-350 4/11/84 2821-F013K 4 Manual 902 PSIC LST 83-350 4/11/84 2821-F013L 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013M 4 Manual 902 PSIC LST 83-350 4/11/84 2821-F013N 4 Manual 902 PSIG LST 83-350 4/11/84 2821-F013P 4 Manual 902 PSIC LST 83-350 4/11/84 2821-F013R 4 Manual 902 PSIC LST 83-350 4/11/84 2B21-F0138 4 Manual 902 PSIG L3T 83-350 4/11/84 2B21-F013U 4 Manual 902 PSIG LST 83-350 4/11/84 2B21-F013V 4 Manual 902 PSIC LST 83-350

.1

'l . 2. ECCS Systems Outag o The following outages were taken on ECCS Systems during

. the reporting period.

OUTAGE NO. EQUIPMENT PURP0;E OF OUTAGE 2-482-84 HPCS Water Leg Pump Replace motor bearings 2-492-84 2E12-F040A Adjust limits 2- 3-84 2A D/G Air Comp. Remove / Repair Motor 2-522-84 2B D/G Repaie Fuel Leak 2-533-84 RHR "A" HI Discharge valve air supply 2-544-84 2A D/G Replaco A/C 011 Circ Pump 2-545-84 2A D/G B Starting Repair A/C 2-546-84 2A D/G A Starting Repair A/C 2-549-84 2E12-F040A Repair Leakage.

2-570-84 RHR "A" HI Upstream vent to S/P.

2-576-84 RHR "A" HI Per T.S. 3.6.3. will not downstream vent close fully with M.0.

to S/P.

3. Off-01te Dose Calculation Manual There wer 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.

l

\

i I

l Document 0043r/0005r _ _ _ _ ___ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ , , . _

?i ? t "E -

N Commonwealth Edison

~cc;) ' Rural Routa #1, Box 220LaSille County Nucitar Station V' Marseilles, Illinois 61341

) Telephone 815/357-6761 May 10, 1984 l

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 April 1 through April 30, 1984.

Very truly yours, c19 G. J. Diederich Superintendent LaSalle County Station GJD/ARL/bej Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jacksoa, CE Resident 55

.

ML20091K481

Contents

Text

R. PROCEDURE

SUMMARY

SUBJECT:

REFERENCE:

Navigation menu

ML20091K481

Text

R. PROCEDURE

SUMMARY

SUBJECT:

REFERENCE:

Navigation menu

Search