ML20153B670: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:,                                                     .                        .-
{{#Wiki_filter:,
          .6 n'
.6 n'
LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JANUARY, 1986 CONT 0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. WPF-11 Doctament 0043r/0005r                         kk2I4hg lh373 R                     PM
LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JANUARY, 1986 CONT 0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. WPF-11 Doctament 0043r/0005r kk2I4hg lh373 R
PM


5 I.               INTRODUCTION 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 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 Edision Company.
5 I.
INTRODUCTION 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 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 Edision Company.
Unit one was issued operating license number NPF-1L on April 17, 1982. Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.
Unit one was issued operating license number NPF-1L 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 James P. Peters, telephone number (815)357-6761 extension 325.
This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.
J .
J.
Document 0043r/0005r
Document 0043r/0005r


T:
T:
                    '-                                                      TABLE OF CONTENTS s.
TABLE OF CONTENTS s.
: 1.       INTRODUCTION II.       MONTHLY REPORT FOR UNIT ONE A.           Summary of Operating Experience B.           PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE
1.
: 1. Asaendiments to Facility License or Technical Specifications
INTRODUCTION II.
: 2. Facility or Procedure Changes Requiring NRC Approval
MONTHLY REPORT FOR UNIT ONE A.
: 3. Tests and Experiinents Requiring NRC Approval
Summary of Operating Experience B.
: 4. Corrective Maintenance of Safety Related Equipement C.           LICENSEE EVENT REPORTS D.           DATA TABULATIONS
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1.
: 1. Operating Data Report
Asaendiments to Facility License or Technical Specifications 2.
: 2. Average Daily Unit Power Level
Facility or Procedure Changes Requiring NRC Approval 3.
: 3. Unit Shutdowns and Power Reductions E.           UNIQUE REPORTING REQUIREMENTS
Tests and Experiinents Requiring NRC Approval 4.
: 1. Main Steasa Relief Valve Operations
Corrective Maintenance of Safety Related Equipement C.
: 2. ECCS System Outages
LICENSEE EVENT REPORTS D.
: 3. Off-Site Dose Calculation Manual Changes
DATA TABULATIONS 1.
: 4. itajor Changes to Radioactive Waste Treatement System l
Operating Data Report 2.
l                     Document 0043r/0005r
Average Daily Unit Power Level 3.
    --    - - , . . , , , , , -  -,,--..,n-     ,,-,,-,,--.---,-~_.--,,,,.,,-,rn---,-,.-,-,w,--,a,~,-w,,,___r,
Unit Shutdowns and Power Reductions E.
                                                                                                                ,,,.,,,-n.,-wgr--n,---,,-,--,,,, .- , - ,. . , ,-
UNIQUE REPORTING REQUIREMENTS 1.
Main Steasa Relief Valve Operations 2.
ECCS System Outages 3.
Off-Site Dose Calculation Manual Changes 4.
itajor Changes to Radioactive Waste Treatement System l
l Document 0043r/0005r
-,,--..,n-
,,-,,-,,--.---,-~_.--,,,,.,,-,rn---,-,.-,-,w,--,a,~,-w,,,___r,
,,,.,,,-n.,-wgr--n,---,,-,--,,,,


1 s
1 s
  ,        -II.                   MONTHLY REPORT FOR UNIT ONE A.                   SUlWUutY OF OPERATING EXPERIENCE FOR UNIT ONE January 1-31 Jan. 1, 0001 Hours.                                           The Unit entered January with the reactor subcritical and g                                                                                               unit-off line in cold shutdown for first refuel outage.
-II.
Jan. 31, 2400 Hours.                                         Reactor in cold shutdown for
MONTHLY REPORT FOR UNIT ONE A.
                                                                                                .Eirst refueling outage.
SUlWUutY OF OPERATING EXPERIENCE FOR UNIT ONE January 1-31 Jan. 1, 0001 Hours.
The Unit entered January with the reactor subcritical and g
unit-off line in cold shutdown for first refuel outage.
Jan. 31, 2400 Hours.
Reactor in cold shutdown for
.Eirst refueling outage.
1 4
1 4
4
4
}
}
i Document 0043r/0005r
i Document 0043r/0005r
                                                                                                                        . ~ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ - - _ _ - - _ -
. ~ _. _ _ _ _ _..


B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED
B.
          - MAINTENANCE.
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED
: 1. Amendments to facility license or Technical Specification.
- MAINTENANCE.
Amendment 32- This revised Unit #1 Technical Speciafication to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.
1.
: 2. Facility or procedure changes requiring NRC approval.
Amendments to facility license or Technical Specification.
Amendment 32-This revised Unit #1 Technical Speciafication to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.
2.
Facility or procedure changes requiring NRC approval.
There were no Facility or Procedure Changes Requiring NRC approval during this reporting period.
There were no Facility or Procedure Changes Requiring NRC approval during this reporting period.
: 3. Tests and Experiments requiring NRC approval.
3.
Tests and Experiments requiring NRC approval.
There were no tests or experiments requiring NRC approval during this reporting period.
There were no tests or experiments requiring NRC approval during this reporting period.
: 4. Corrective maintenance of safety related equipment.
4.
Corrective maintenance of safety related equipment.
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 number, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.
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 number, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.
Document 0043r/0005r
Document 0043r/0005r


R TABLE 1                                                     ,
R TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED'BQUIPMENT WORK REQUEST 00ffCNENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L20781 Prelube Pump for "0"
CORRECTIVE MAINTENANCE OF SAFETY RELATED'BQUIPMENT WORK REQUEST   00ffCNENT             CAUSE OF MALFUNCTION           RESULTS AND EFFECTS           CORRECTIVE ACTION ON SAFE PLANT OPERATION L20781       Prelube Pump for "0" Per Tech. Spec. 3.8.1.1/2   Preclude. dry-starting of       M-1-0-83-026 completed.
Per Tech. Spec. 3.8.1.1/2 Preclude. dry-starting of M-1-0-83-026 completed.
DG, ODG0lK                                         Diesel Engine.
DG, ODG0lK Diesel Engine.
L20784       Prelube pump for "lB" Per Tech. Spec. 3.8.1.1/2   Preclude dry-starting of         M-1-1-82-319 completed.
L20784 Prelube pump for "lB" Per Tech. Spec. 3.8.1.1/2 Preclude dry-starting of M-1-1-82-319 completed.
DG, IDG02K.                                       Diesel Engine.                                             ,
DG, IDG02K.
L20786       Controls and Instr. Per Tech. Spec. 3.8.1.1/2   Mount on vibration free floor   M-1-0-82-132 completed.
Diesel Engine.
for ODG, ODGOIK.                                   or vibration mounts.
L20786 Controls and Instr.
L20788       Controls and Instr. Per Tech. Spec. 3.8.1.1/2   Mount on vibration free floor   M-1-1-82-309 completed.
Per Tech. Spec. 3.8.1.1/2 Mount on vibration free floor M-1-0-82-132 completed.
for "lB" DG, IDG02K.                               or vibration mounts.
for ODG, ODGOIK.
L38021       Post LOCA H2 recom-   Envionmental Qualification. Move H2 recombiner power         M-1-1-84-079 completed, biner power cabinet                               cabinet to a milder environment.
or vibration mounts.
L20788 Controls and Instr.
Per Tech. Spec. 3.8.1.1/2 Mount on vibration free floor M-1-1-82-309 completed.
for "lB" DG, IDG02K.
or vibration mounts.
L38021 Post LOCA H2 recom-Envionmental Qualification. Move H2 recombiner power M-1-1-84-079 completed, biner power cabinet cabinet to a milder environment.
IPLF3J.
IPLF3J.
L52734       "0" DG Cooling Water Packing Leak at valve.       No potential effect.             Repacked valve.
L52734 "0" DG Cooling Water Packing Leak at valve.
No potential effect.
Repacked valve.
upstream stop ODG006.
upstream stop ODG006.
L54555       Mechanical Snubber   Bad snt.bber.                 Failed LTS-500-14.             Replaced snubber.
L54555 Mechanical Snubber Bad snt.bber.
Failed LTS-500-14.
Replaced snubber.
MsC6-10165.
MsC6-10165.
L54641       "1B" DG Panel         Wire lar.ied on wrong         No potential effect.           Wired per drawing IE22-P301B.           terminal block.               Due to M-1-1-82-319.           in modification.
L54641 "1B" DG Panel Wire lar.ied on wrong No potential effect.
L54682       "1B" HPCS Diesel     Wire landed on wrong         No potential effect,           Wired per drawing IE22-F301B.           terminal block.               Due to M-1-1-82-319.           in modification.
Wired per drawing IE22-P301B.
L54912       LPRM 6A-32-09         Downscale light on full       False downscale indications. Replaced transister APRM F             core display would not                                       on circuit card.
terminal block.
Due to M-1-1-82-319.
in modification.
L54682 "1B" HPCS Diesel Wire landed on wrong No potential effect, Wired per drawing IE22-F301B.
terminal block.
Due to M-1-1-82-319.
in modification.
L54912 LPRM 6A-32-09 Downscale light on full False downscale indications.
Replaced transister APRM F core display would not on circuit card.
clear in bypass.
clear in bypass.
L54913       LPRM 1A-16-57         Drifting upscale and         No potential effect, full       Replaced upscale and APRM-F.               Downscale points.             core display worked properly. downscale comparator.
L54913 LPRM 1A-16-57 Drifting upscale and No potential effect, full Replaced upscale and APRM-F.
Downscale points.
core display worked properly.
downscale comparator.
DOCUMENT 0044r/0005r
DOCUMENT 0044r/0005r


i TABLE 1                                                     ,
i TABLE 1 CORRECTIVE MAINTENANCE OF
CORRECTIVE MAINTENANCE OF
~
                                                                                                                                            ~
SAFETY RELATED BQUIPfEENT WORK REQUEST C0ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION s
SAFETY RELATED BQUIPfEENT WORK REQUEST             C0ff0NENT               CAUSE OF MALFUNCTION           RESULTS AND EFFECTS           CORRECTIVE ACTION ON SAFE PLANT OPERATION s
L54914 LPRM 56-48-17 The downscale light on full Failure of applicable portions-- Repaired circuit card.
L54914               LPRM 56-48-17           The downscale light on full Failure of applicable portions-- Repaired circuit card.
LPRM A core display would not of LIS-NR-ll6.
LPRM A                 core display would not       of LIS-NR-ll6.
energize.
energize.
t
t L54D15
:      L54D15              .LPRM SC-48-25           Bad lamp and no divider     No potential effect, all lights Installed light divider APRM B               .between SC-48-25 and         on back panel worked.           and replaced lamp.
.LPRM SC-48-25 Bad lamp and no divider No potential effect, all lights Installed light divider APRM B
.between SC-48-25 and on back panel worked.
and replaced lamp.
5D-48-25.
5D-48-25.
l     L54916               LPRM 5A-40-25           Poor solder connection on   Sporadic light indication.     Resoldered bad APRM E                 circuit board,                                               connection on circuit.
l L54916 LPRM 5A-40-25 Poor solder connection on Sporadic light indication.
Resoldered bad APRM E circuit board, connection on circuit.
board.
board.
1     L54975               Fuel Oil transfer       Blind Flange orifice         LTS-1000-24 satisfactorily. Replaced orifice plate.
1 L54975 Fuel Oil transfer Blind Flange orifice LTS-1000-24 satisfactorily.
pump recirc. orifice     plate for LTS-1000-24.
Replaced orifice plate.
!                            Plate OD08M.
pump recirc. orifice plate for LTS-1000-24.
L55129               "0" DG Pressure Switch OPSL-DG046/50. piped off     No. potential effect, per       Repiped pressure switches.
Plate OD08M.
j                           piping ODG0lK.           discharge of oil pump,       per M-1-0-83-026.
L55129 "0" DG Pressure Switch OPSL-DG046/50. piped off No. potential effect, per Repiped pressure switches.
;                                                    should be piped to turbo charger.
j piping ODG0lK.
discharge of oil pump, per M-1-0-83-026.
should be piped to turbo charger.
?
?
L55132               Chlorine detector       Dirty Detector Tank and       Failed LIS-VC-01.             Cleaned detector tank oAE-VC-090A.             bad wick.                                                     and. replaced wick.
L55132 Chlorine detector Dirty Detector Tank and Failed LIS-VC-01.
1 L55371               containment Monitor     Toe large of deviation be-   Indecision in indication,       Replaced ITI-CM040.
Cleaned detector tank oAE-VC-090A.
ITR-CM037/40.           tween ITR-CM037 and           failed LIP-RX-02.
bad wick.
and. replaced wick.
1 L55371 containment Monitor Toe large of deviation be-Indecision in indication, Replaced ITI-CM040.
ITR-CM037/40.
tween ITR-CM037 and failed LIP-RX-02.
ITR-CM040.
ITR-CM040.
L55405                 *0" DG Lube oil Pump   Thermal overload relay was Failure of LES-AP-01.             Replaced thermal breaker 7A.             bed.                                                         overload relay.
L55405
L55582               Control Room HVAC       Dirt on clogged oil filter. HVAC unit keeps tripping on       Cleaned out filter.
*0" DG Lube oil Pump Thermal overload relay was Failure of LES-AP-01.
OVC04CA.                                             Iow oil pressure.
Replaced thermal breaker 7A.
bed.
overload relay.
L55582 Control Room HVAC Dirt on clogged oil filter. HVAC unit keeps tripping on Cleaned out filter.
OVC04CA.
Iow oil pressure.
i DOCUMENT 0044r/0005r
i DOCUMENT 0044r/0005r


l C. LICENSEE EVENT REPORTS l
l C.
l The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, January 1 through January 31, 1986. This inforination is provided pursuant to the reportable occurrence reporting requireinents as set forth in 10CFR 50.73.
LICENSEE EVENT REPORTS l
Licensee Event ReDort MUInber     Date   Title of Occurrence There were no licensee event reports in this reporting period.
The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, January 1 through January 31, 1986. This inforination is provided pursuant to the reportable occurrence reporting requireinents as set forth in 10CFR 50.73.
Licensee Event ReDort MUInber Date Title of Occurrence There were no licensee event reports in this reporting period.
Docusment 0043r/0005r
Docusment 0043r/0005r


l 4
4 D.
D. DATA TABULATIODIS The following data tabulations are presented in this report:
DATA TABULATIODIS The following data tabulations are presented in this report:
: 1. Operating Data Report
1.
: 2. Average Daily Unit Power Level
Operating Data Report 2.
: 3. Unit Shutdowns and Power Reductions J
Average Daily Unit Power Level 3.
Unit Shutdowns and Power Reductions J
Doctament 0043r/0005r
Doctament 0043r/0005r
: 1. OPERATING DATA REPORT DOCKET NO. 050-373
 
,                                                                UNIT LaSalle One DATE February 7, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1.
: 1. REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744
OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE February 7, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS 1.
: 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):]R1 MAX DEPEND CAPACITY (MWe-Net): 1036   DESIGN ELECTRICAL RATING (MWe-Net): 1078
REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744 2.
: 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net):       N/A
CURRENTLY AUTHORIZED POWER LEVEL (MWt):]R1 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 3.
: 4. REASONS FOR RESTRICTION (IF ANY):     N/A THIS MONTH YR TO DATE     CUMULATIVE 5     NUMBER OF HOURS REACTOR WAS CRITICAL     0.0         0.0       12039.00
POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net):
: 6. REACTOR RESERVE SHUTDOWN HOURS           0.0         0.0         1642.00
N/A 4.
: 7. HOURS GENERATOR ON LINE                   0.0         0.0       11642.00
REASONS FOR RESTRICTION (IF ANY):
: 8. UNIT RESERVE SHUTDOWN HOURS               0.0         0.0         0.0
N/A THIS MONTH YR TO DATE CUMULATIVE 5
: 9. GROSS THERMAL ENERGY GENERATED (MWH)     0.0         0.0       32213650
NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 12039.00 6.
: 10. GROSS ELEC. ENERGY GENERATED (MWH)         0.0         0.0       10499394
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.00 7.
: 11. NET ELEC. ENERGY GENERATED (MWH)         -5582       -5582       9998875
HOURS GENERATOR ON LINE 0.0 0.0 11642.00 8.
: 12. REACTOR SERVICE FACTOR                   0.0%         0.0%         65.7%
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.
: 13. REACTOR AVAILABILITY FACTOR               0.0%         0.0%         74.7%
GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 32213650
: 14. UNIT SERVICE FACTOR                       0.0%         0.0%         63.6%
: 10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 10499394
: 15. UNIT AVAILABILITY FACTOR                 0.0%         0.0%         63.6%
: 11. NET ELEC. ENERGY GENERATED (MWH)
: 16. UNIT CAPACITY FACTOR (USING MDC)         -0.72%       -0.72%         52.7%
-5582
: 17. UNIT CAPACITY FACTOR (USING DESIGN MWe)                                   -0.69%       -0.69%         50.6%
-5582 9998875
: 18. UNIT FORCED OUTAGE RATE                   0.0%         0.0%         17.4%
: 12. REACTOR SERVICE FACTOR 0.0%
0.0%
65.7%
: 13. REACTOR AVAILABILITY FACTOR 0.0%
0.0%
74.7%
: 14. UNIT SERVICE FACTOR 0.0%
0.0%
63.6%
15.
UNIT AVAILABILITY FACTOR 0.0%
0.0%
63.6%
16.
UNIT CAPACITY FACTOR (USING MDC)
-0.72%
-0.72%
52.7%
17.
UNIT CAPACITY FACTOR (USING DESIGN MWe)
-0.69%
-0.69%
50.6%
: 18. UNIT FORCED OUTAGE RATE 0.0%
0.0%
17.4%
: 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
: 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
The First Refueling Maintenance, surveillance and Modification Outage began October 18, 1985 and will last 30 weeks.
The First Refueling Maintenance, surveillance and Modification Outage began October 18, 1985 and will last 30 weeks.
: 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: May, 1986 Document 0043r/0005r
20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: May, 1986 Document 0043r/0005r


f
f
: 2. AVERAGE DAILY UNIT POWER LEVEL
: 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: February 7. 1986 COMPLETED BY: Jenes P. Peters TELEPHONE: (815) 357-6761 MONTH: JANUARY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met)
    ,'                                                                                                                            DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: February 7. 1986 COMPLETED BY: Jenes P. Peters TELEPHONE: (815) 357-6761 MONTH: JANUARY 1986 DAY AVERAGE DAILY POWER LEVEL                                                                                 DAY AVERAGE DAILY POWER LEVEL (MWe-Met)                                   (MWe-Net)
(MWe-Net) 1.
: 1.                                                               -5                           17.         -6
-5 17.
: 2.                                                                 -5                           18.         -8 3                                                                   -6                           19.         -5
-6 2.
: 4.                                                                 -7                           20.         -5
-5 18.
: 5.                                                                 -4                           21.         -5
-8 3
: 6.                                                                 -4                           22.         -12
-6 19.
                          't .                                                               -3                           23.         -13
-5 4.
: 8.                                                                 -4                           24.         -14
-7 20.
: 9.                                                                 -4                           25.         -13
-5 5.
: 10.                                                                         -4                           26.         -14
-4 21.
: 11.                                                                         -5                           27.         -14
-5 6.
: 12.                                                                         -3                           28.         -14
-4 22.
: 13.                                                                         -4                           29.         -14
-12
: 14.                                                                         -4                           30.         -13
't.
: 15.                                                                         -4                           31.         -13
-3 23.
: 16.                                                                         -3 Document 0043r/0005r
-13 8.
-4 24.
-14 9.
-4 25.
-13 10.
-4 26.
-14 11.
-5 27.
-14 12.
-3 28.
-14 13.
-4 29.
-14 14.
-4 30.
-13 15.
-4 31.
-13 16.
-3 Document 0043r/0005r


                                                                                                      -                              a ATTACIDENT E                                                             ,
a ATTACIDENT E 3.
: 3. UNIT SHUTDOWS AND POWER REDUCTIONS DOCKET NO. 050-373               ;
UNIT SHUTDOWS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAM LaSalle One DATE FEBRUARY 7.
,                                                                                                    UNIT NAM LaSalle One DATE FEBRUARY 7. 1986
1986 REPORT MONTH JANUARY 1986 COfFLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.
,                                                REPORT MONTH JANUARY 1986                           COfFLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF
DATE S:. SCHEDULED (HOURS)
;                          TYPE                                                     SHUTTING DOWN F: FORCED           DURATION                               THE REACTOR OR         CORRECTIVE NO.     DATE         S:. SCHEDULED       (HOURS)         REASON                 REDUCING POWBd         ACTIONS /COf9EENTS There were no Unit shutdowns or power reductions during this reporting period.
REASON REDUCING POWBd ACTIONS /COf9EENTS There were no Unit shutdowns or power reductions during this reporting period.
i~                         i i       ;    -                        !
i~
                                                          ~
i i
f  -
f
~
m m
m m
                                                                        ~                                               .
~
                    ~
~
* a As DOCUMENT 0044r/0005r
a As DOCUMENT 0044r/0005r


E. UNIQUE REPORTING REQUIREMIDITS
E.
                                  \         '
UNIQUE REPORTING REQUIREMIDITS
\\
: 1. Safety / Relief valva operations for Unit One.
: 1. Safety / Relief valva operations for Unit One.
                      ' VALVES             NO & TYPE PLANT       DESCRIPTION DATE           ACTUATED           ACTUATION CONDITION   OF EVENT There were no Safety R911ef Valves Operated for Unit One during this reporting period.
' VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety R911ef Valves Operated for Unit One during this reporting period.
J
J
~
~
1
1
                              \
\\
s e
s e
1 1
1 1
4 i,
4 i,
s i
s i
                    ,                i Doctament 0043r/0005r t
i Doctament 0043r/0005r t


s
s 2.
: 2. ECCS Systems Outrge3
ECCS Systems Outrge3 The following outages were taken on ECCS Systems during the reporting period.
  ,              The following outages were taken on ECCS Systems during the reporting period.
OUTAGE NO.
OUTAGE NO.             BOUIPMENT               PURPOSE OF OUTAGE 0-8-86                 "0"D/G                   Calibration of speed tachometer 0-24-86               Security D/G             Annual Inspection 1-2-86               "0"D/G Fuel Oil Transfer Change orifice Pump 1-4-86               1E12-F021               LES-BQ-112 1-5-86               IE12-F042C               LES-BQ-112 1-6-86               1812-F042C               1E12-F327C 1-7-86               1E12-F042C               Worm Gear Inspection 1-8-86               "0" D/G                 Recondition Air Start Motors 1-14-86               1E51-F066               Repair Position Indicator 1-29-86               "A" RHR System           Replace Pump Shaft 1-33-86               1821-F001               LES-BQ-112 1-35-86               SDC Line                 Repair 1812-F008/9 1-36-86               1E22-F011               LES-BQ-112 1-37-86               1822-F015               LES-BQ-112 1-38-86               1E22-F001               LES-BQ-ll2 1-39-86               1E12-F009               LES-BQ-112 1-40-86               1E12-F008               LES-BQ-112 1-41-86               IE12-F006A               LES-BQ-112 1-42-86               1E12-F006B               LES-BQ-112 1-43-86               1E51-F063               Repack Valve 1-44-86               IE21-F001               Remove Limitorque 1-49-86               "C" RHR                 Replace Puffer Piston 1-50-86               IE12-F004A               Change Grease 1-51-86               1E12-F016A               Repair Valve 1-52-86               IE12-F024B               Repack Valve 1-53-86               IE12-F020               Prevent Drawing Vessel 1-54-86               1E12-F064A               Repack Valve 1-55-86               1812-F064A               LES-BQ-il2 1-56-86               1E12-F004A               LES-BQ-112 1-57-86               1E12-F312A               LES-BQ-112 1-58-86               1812-F312B               LES-BQ-112 1-59-86               143-1 Feed Breaker       Inspect Breaker 1-62-86               IB D/G                   Repair Air Start Motor 1-63-86               1E22-5003               Inspect Breaker 1-64-86               RCIC                     Replace Drain Pot Level Instrument Isolation Valves 1-65-86               "1B" RHR HX Service     Hydrolaze HX water Side 1-66-86               LE12-F046C               Inspection 1-67-86               lE12-F003A               LES-BQ-112 1-68-86               1E12-F016A               LES-BQ-112 1-69-86               1E12-F023               LES-BQ-112 1-70-86               1E12-F024A               LES-BQ-112 Document 0043r/0005r
BOUIPMENT PURPOSE OF OUTAGE 0-8-86 "0"D/G Calibration of speed tachometer 0-24-86 Security D/G Annual Inspection 1-2-86 "0"D/G Fuel Oil Transfer Change orifice Pump 1-4-86 1E12-F021 LES-BQ-112 1-5-86 IE12-F042C LES-BQ-112 1-6-86 1812-F042C 1E12-F327C 1-7-86 1E12-F042C Worm Gear Inspection 1-8-86 "0" D/G Recondition Air Start Motors 1-14-86 1E51-F066 Repair Position Indicator 1-29-86 "A" RHR System Replace Pump Shaft 1-33-86 1821-F001 LES-BQ-112 1-35-86 SDC Line Repair 1812-F008/9 1-36-86 1E22-F011 LES-BQ-112 1-37-86 1822-F015 LES-BQ-112 1-38-86 1E22-F001 LES-BQ-ll2 1-39-86 1E12-F009 LES-BQ-112 1-40-86 1E12-F008 LES-BQ-112 1-41-86 IE12-F006A LES-BQ-112 1-42-86 1E12-F006B LES-BQ-112 1-43-86 1E51-F063 Repack Valve 1-44-86 IE21-F001 Remove Limitorque 1-49-86 "C" RHR Replace Puffer Piston 1-50-86 IE12-F004A Change Grease 1-51-86 1E12-F016A Repair Valve 1-52-86 IE12-F024B Repack Valve 1-53-86 IE12-F020 Prevent Drawing Vessel 1-54-86 1E12-F064A Repack Valve 1-55-86 1812-F064A LES-BQ-il2 1-56-86 1E12-F004A LES-BQ-112 1-57-86 1E12-F312A LES-BQ-112 1-58-86 1812-F312B LES-BQ-112 1-59-86 143-1 Feed Breaker Inspect Breaker 1-62-86 IB D/G Repair Air Start Motor 1-63-86 1E22-5003 Inspect Breaker 1-64-86 RCIC Replace Drain Pot Level Instrument Isolation Valves 1-65-86 "1B" RHR HX Service Hydrolaze HX water Side 1-66-86 LE12-F046C Inspection 1-67-86 lE12-F003A LES-BQ-112 1-68-86 1E12-F016A LES-BQ-112 1-69-86 1E12-F023 LES-BQ-112 1-70-86 1E12-F024A LES-BQ-112 Document 0043r/0005r


CUTAGE NO.                                               BOUIPMENT                                         PURPOSE OF OUTAGE 1-71-86                                                   1E12-F027A                                       LES-Bg-112 1-72-86                                                   1E12-F040A-                                     LES-BQ-112 1-73-86                                                   1E12-F047A                                       LES-Bg-112                   l 1-74-86                                                   1E12-PO48A                                       LES-BQ-112 1-75-86                                                   1812-F053A                                       LES-BD-112 1-76-86                                                   1E12-F099A                                       LES-Bg-112
CUTAGE NO.
                      ,    1-77-86                                                   1DG035                                           Flush Gear Casing 1-19-86                                                   IE12-F024A                                       Repack Valve 1-81-86                                                 "1B"D/G Breaker 143-3                             Inspect Breaker
BOUIPMENT PURPOSE OF OUTAGE 1-71-86 1E12-F027A LES-Bg-112 1-72-86 1E12-F040A-LES-BQ-112 1-73-86 1E12-F047A LES-Bg-112 1-74-86 1E12-PO48A LES-BQ-112 1-75-86 1812-F053A LES-BD-112 1-76-86 1E12-F099A LES-Bg-112 1-77-86 1DG035 Flush Gear Casing 1-19-86 IE12-F024A Repack Valve 1-81-86 "1B"D/G Breaker 143-3 Inspect Breaker 1-82-86 "1B" D/G Replace Diode 1-89-86 1E12-F327A Remove Testable Check Valve 1~91-86 LE12-PO41A Repair Testable Check 1-92-86 IE12-F063B Fill "B" RHR
;                          1-82-86                                                 "1B" D/G                                         Replace Diode 1-89-86                                                 1E12-F327A                                       Remove Testable Check Valve 1~91-86                                                   LE12-PO41A                                       Repair Testable Check 1-92-86                                                   IE12-F063B                                       Fill "B" RHR
'(
                  '(       1-93-86                                                   1821-F041C                                       Fix Actuator 1-97-86                                                   1812-F063B                                       Keep "B" RHR   Filled 1-108                                               1812-F003B                                       LES-BQ-112 1-109-86                                                 1812-F040B                                     -LES-BQ-112 1-110-86                                                 1812-F064B                                       LES-BQ-112 1-111-86                                                 1E12-F094                                         LES-BO-112 1-114-86                                                 "1B" RHR Pump                                     Replace Puffer Piston 1-115-86                                                 "1B" RHR Pump                                     LES-EQ-112 1-116-86                                                 1E12-F004B                                       LES-BQ-112 1-117-86                                                 1812-F017B                                       LES-BQ-112 1-118-86                                                 1812-F024B                                       LES-ag-112 1-119-86                                                 1812-F027B                                       LES-Bg-112 i   \                     1-120-86                                                 1812-F042B                                       LES-Bg-112                 ,
1-93-86 1821-F041C Fix Actuator 1-97-86 1812-F063B Keep "B" RHR Filled 1-108 1812-F003B LES-BQ-112 1-109-86 1812-F040B
1-121-86                                                 1E12-F047B                                       LES-BQ-112                 l 1-122-86                                                 1E12-F048B                                       LES-BQ-112 1-123-86                                                 1E12-F053B                                       LES-BQ-112 1-124-86                                                 IE12-F099B                                       LES-BQ-112 1-129-86                                                 1812-F402B                                       Locked Valve Tracking 1-132-86                                               "1A" D/G                                         Prelube; Modification 1-133                                               "1A" D/G                                         Protective Relay Calibrations 1-134-86                                                 "1A" D/G                                         Replace Pressure Switch 1-135-86                                                 "1A" D/G                                         Replace Puffer Piston
-LES-BQ-112 1-110-86 1812-F064B LES-BQ-112 1-111-86 1E12-F094 LES-BO-112 1-114-86 "1B" RHR Pump Replace Puffer Piston 1-115-86 "1B" RHR Pump LES-EQ-112 1-116-86 1E12-F004B LES-BQ-112 1-117-86 1812-F017B LES-BQ-112 1-118-86 1812-F024B LES-ag-112 1-119-86 1812-F027B LES-Bg-112 i
                          'l-137-86                                                 1851-N009A/9B/12A-D/20                           E.Q. Switch Replace 1-159-86                                                 1812-F099B                                       Remove Valve.
\\
1-160-86                                                 1812-F026B                                       Replace Handwheel 1-162-86                                                 "B" RHR Service Water                             Install Isolation Valves 1-163-86                                                 HPCS                                             M-1-1-82-292 1-166-86                                                 1821-N005                                       Revise Switch Logic 1-167-86                                                 1E12-F046A                                       Inspection 4
1-120-86 1812-F042B LES-Bg-112 1-121-86 1E12-F047B LES-BQ-112 l
1-168-86                                                 "1C" RHR Pump                                     Change Oil 1-169-86                                                 HPCS Pump                                         Change Oil 1-173-86                                                 "B" RHR Service Water                             Repack Valve Strainer 1-174-86                                                 1812-F050A                                       Repack Valve 1-175-86                                                 IE12-F042B                                       Inspect Operator 1-177-86                                                 1E22-N001A/B                                     E.Q. Switch Replace 1-178-86                                                 1851-N010 -                                     E.Q. Switch Replace 1-179-86                                                 LE22-N002A/B                                     E.Q. Switch Replace
1-122-86 1E12-F048B LES-BQ-112 1-123-86 1E12-F053B LES-BQ-112 1-124-86 IE12-F099B LES-BQ-112 1-129-86 1812-F402B Locked Valve Tracking 1-132-86 "1A" D/G Prelube; Modification 1-133 "1A" D/G Protective Relay Calibrations 1-134-86 "1A" D/G Replace Pressure Switch 1-135-86 "1A" D/G Replace Puffer Piston
;                          1-180-86                                                 IE51-NO35A/E                                     E.Q. Switch Replace Document 0043r/0005r
'l-137-86 1851-N009A/9B/12A-D/20 E.Q. Switch Replace 1-159-86 1812-F099B Remove Valve.
_,        ~_ . --    _ - . ~ ~ . ~ . _ . _ . _ _ - _ - _ . , . _ . _ _ _ . - _ . _ _ . . . ~ . - _ . . . - _ _ . _ _ _
1-160-86 1812-F026B Replace Handwheel 1-162-86 "B" RHR Service Water Install Isolation Valves 1-163-86 HPCS M-1-1-82-292 1-166-86 1821-N005 Revise Switch Logic 1-167-86 1E12-F046A Inspection 4
1-168-86 "1C" RHR Pump Change Oil 1-169-86 HPCS Pump Change Oil 1-173-86 "B" RHR Service Water Repack Valve Strainer 1-174-86 1812-F050A Repack Valve 1-175-86 IE12-F042B Inspect Operator 1-177-86 1E22-N001A/B E.Q. Switch Replace 1-178-86 1851-N010 -
E.Q. Switch Replace 1-179-86 LE22-N002A/B E.Q. Switch Replace 1-180-86 IE51-NO35A/E E.Q. Switch Replace Document 0043r/0005r
~
_ -. ~ ~. ~. _. _. _ _ - _ - _.,. _. _ _ _. - _. _ _... ~. - _... - _ _. _ _ _


OUTAGE NO.             EQUIPMENT                                   PURPOSE OF OUTAGE 1-184-86             1812-F0463                                   Inspection
OUTAGE NO.
  ,'        1-187-86             1812-F312A                                   Rotate Liinitorque 1-188-86             1E12-F011B                                   Reinstall Handwheel                   j 1-189-86             1DG01P                                       Inspect Motor
EQUIPMENT PURPOSE OF OUTAGE 1-184-86 1812-F0463 Inspection 1-187-86 1812-F312A Rotate Liinitorque 1-188-86 1E12-F011B Reinstall Handwheel j
                                                                                      ~
1-189-86 1DG01P Inspect Motor
1-191-86             1E22-F015                                   Rotate Operator 1-196-86_             1812-F041B                                   Rebuild Operator                     i 1-198-86             1851-N002A                                   E.Q. Mod 1-199-86             IE12-F026B                                   Handwheel Problem 1-200-86             1E12-F027B                                   Remove Screw 1-201-86             1E12-F027A                                   Rotate Limitorque 1-203-86             1E21-F012                                   LTS-600-3 1-208-86             "B" RHR                                     Change Motor Oil 1-211-86             "1A" D/G Fuel Oil                           Remove Orifice xfer Pump Document 0043r/0005r
~
1-191-86 1E22-F015 Rotate Operator 1-196-86_
1812-F041B Rebuild Operator i
1-198-86 1851-N002A E.Q. Mod 1-199-86 IE12-F026B Handwheel Problem 1-200-86 1E12-F027B Remove Screw 1-201-86 1E12-F027A Rotate Limitorque 1-203-86 1E21-F012 LTS-600-3 1-208-86 "B" RHR Change Motor Oil 1-211-86 "1A" D/G Fuel Oil Remove Orifice xfer Pump Document 0043r/0005r


3 Off-Sito Dose Calculition Manual There were no changes to the ODCM during this reporting period.
3 Off-Sito Dose Calculition Manual There were no changes to the ODCM during this reporting period.
: 4. Radioactive Waste Treatment Systems.
4.
Radioactive Waste Treatment Systems.
There were no significant changes to the radioactive waste treatment system during this reporting period.
There were no significant changes to the radioactive waste treatment system during this reporting period.
t i
t i
Line 224: Line 333:
Document 0043r/0005r
Document 0043r/0005r


i 4   ,,
i 4
LASPLLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT i                                                                                       JANUARY 1986 COttt0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF--18 i
LASPLLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT i
JANUARY 1986 COttt0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF--18 i
t f
t f
I i
I i
t l'
t l'
DOCUh3NT ID 0036t/0005r
DOCUh3NT ID 0036t/0005r
        . . _ . _ . _ _ _ _ _ - . _ _ _ _ _ . . _ . , - - - - -_ _ _ . . - _ . . . , _ -                  -_.___ . _ _ _ _ - _ - . ~ . . , . . _ . . , . . - -
-_.___. _ _ _ _ - _ -. ~..,.. _..


    ,'    I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Cosumonwealth Edison Company and located near Marseilles, 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, i
I.
INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Cosumonwealth Edison Company and located near Marseilles, 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, i
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.
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 James P. Peters, telephone number (815)357-6761 extension 325.
This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.
Line 238: Line 349:
DOCUMENT ID 0036r/0005r
DOCUMENT ID 0036r/0005r


TABLE OF CONTENTS
TABLE OF CONTENTS 1.
: 1. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A.     Summary of Operating Experience B.     PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE
INTRODUCTION II.
: 1. Amendments to Facility License or Technical Specifications
MONTHLY REPORT FOR UNIT TWO A.
: 2. Facility or Procedure Changes Requiring NRC Approval
Summary of Operating Experience B.
: 3. Tests and Experiments Requiring NRC Approval
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1.
: 4. Corrective Maintenance of Safety Related Equipment C.     LICENSEE EVENT REPORTS D.     DATA TABULATIONS
Amendments to Facility License or Technical Specifications 2.
: 1. Operating Data Report
Facility or Procedure Changes Requiring NRC Approval 3.
: 2. Average Daily Unit Power Level
Tests and Experiments Requiring NRC Approval 4.
: 3. Unit Shutdowns and Power Reductions E.     UNIQUE REPORTING REQUIREMENTS
Corrective Maintenance of Safety Related Equipment C.
: 1. Safety / Relief Valve Operations
LICENSEE EVENT REPORTS D.
: 2. ECCS System Outages
DATA TABULATIONS 1.
: 3. Off-Site Dose Calculation Manual Changes
Operating Data Report 2.
: 4. Major Changes to Radioactive Waste Treatment System I
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.
Major Changes to Radioactive Waste Treatment System I
DOCUMENT ID 0036r/0005r
DOCUMENT ID 0036r/0005r
                          -. ..      .  . ~ _ , _ _ _ - .   . _ .- - _ , _ _ _ _ _ . - . -- . _ . . _ _ _ . _ _ - , _ . _
. ~ _, _ _ _ -.


II. MONTHLY REPORT FOR UNIT TWO
II.
      *A. SUtetARY OF OPERATING EXPERIENCE FOR UNIT TWO January 1-31 Jan. 1, 0001 Hours. The Unit entered January with the reactor critical at 88% power and generator on-line at 886 MWe.
MONTHLY REPORT FOR UNIT TWO
Jan. 3, 1405 Hours.   "A" TDRFP tripped and power dropped to 53% (592 MWe).
*A.
Jan. 3, 2300 Hours. Power recovered to 89% (890 MWe) and limited due to work in the heater bay.
SUtetARY OF OPERATING EXPERIENCE FOR UNIT TWO January 1-31 Jan. 1, 0001 Hours.
Jan. 9, 1400 Hours. Reactor Power increased to 97%
The Unit entered January with the reactor critical at 88% power and generator on-line at 886 MWe.
Jan. 3, 1405 Hours.
"A" TDRFP tripped and power dropped to 53% (592 MWe).
Jan. 3, 2300 Hours.
Power recovered to 89% (890 MWe) and limited due to work in the heater bay.
Jan. 9, 1400 Hours.
Reactor Power increased to 97%
(1060 MWe).
(1060 MWe).
Jan. 9. 1430 Hours. Reactor Power dropped to 92% (1014 MWe) due to RR controller problems.
Jan. 9. 1430 Hours.
Jan. 9, '300 Hours. Reactor Power restored to 96%
Reactor Power dropped to 92% (1014 MWe) due to RR controller problems.
Jan. 9,
'300 Hours.
Reactor Power restored to 96%
(1050 MWe).
(1050 MWe).
Jan. 10, 0500 Hours. Reactor Power dropped to 93% (1020 MWe) due to heater drain problems.
Jan. 10, 0500 Hours. Reactor Power dropped to 93% (1020 MWe) due to heater drain problems.
Line 276: Line 402:
Jan. 25, 1040 Hours. Reactor Power reduced to 17% (224 MWe) due to bypass valve problem.
Jan. 25, 1040 Hours. Reactor Power reduced to 17% (224 MWe) due to bypass valve problem.
Jan. 27, 0700 Hours. Reactor Power restored to 82% (920 MWe).
Jan. 27, 0700 Hours. Reactor Power restored to 82% (920 MWe).
Jan. 27, 1120 Hours. Reactor Power reduced to 64% (719 MWe) for survie11ance testing, i           Jan. 29, 2000 Hours. Reactor Power increased to full power at 99% (1080 MWe).
Jan. 27, 1120 Hours. Reactor Power reduced to 64% (719 MWe) for survie11ance testing, i
l           Jan. 30, 2100 Hours. Reactor Power reduced to 80% (900 MWe) for control rod manipulation.
Jan. 29, 2000 Hours. Reactor Power increased to full power at 99% (1080 MWe).
l Jan. 30, 2100 Hours. Reactor Power reduced to 80% (900 MWe) for control rod manipulation.
Jan. 31, 2400 Hours. Reactor Power at full power at 100% (1118 MWe).
Jan. 31, 2400 Hours. Reactor Power at full power at 100% (1118 MWe).
I DOCUMENT ID 0036r/0005r
I DOCUMENT ID 0036r/0005r


      ,  'O .          PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.
'O PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.
: 1. Amendments to facility license or Technical Specification.
1.
Amendment 18- This revised Unit 2 Technical Specification to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.
Amendments to facility license or Technical Specification.
4
Amendment 18-This revised Unit 2 Technical Specification to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.
: 2. Facility or procedure changes requiring NRC approval.
4 2.
Facility or procedure changes requiring NRC approval.
There were no facility or procedure change requiring NRC approval during the reporting period.
There were no facility or procedure change requiring NRC approval during the reporting period.
: 3. Tests and experiments requiring NRC approval.
3.
Tests and experiments requiring NRC approval.
There were no tests or experiments requiring NRC approval during the reporting period.
There were no tests or experiments requiring NRC approval during the reporting period.
: 4. Corrective Maintenance of Safety Related Equipment.
4.
Corrective Maintenance of Safety Related Equipment.
The following table (Table 1) presents a summary of safety-related maintenance completed.on Unit Two during tha reporting period. The headings indicated in this susmaary include: Nork Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.
The following table (Table 1) presents a summary of safety-related maintenance completed.on Unit Two during tha reporting period. The headings indicated in this susmaary include: Nork Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.
DOCUMENT ID 0036r/0005r
DOCUMENT ID 0036r/0005r
_-. ._      _ - . _ , _      ,    , _ , . _ _ . ~         __  _.-_,  -- _._    . - _ . -. _ . . . , _ _ _ _ . _ _ .    - , - _ - _ .
, _,. _ _. ~


TABLE 1                                                       ,
TABLE 1 CORRECTIVE MAINTENANCE OF 2
2                                                    CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST   COMPONENT               CAUSE OF MALFUNCTION               RESULTS AND EFFECTS         CORRECTIVE ACTION ON SAFE PLANT OPERATION
SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L38020 Post LOCA H2 recom- '
* L38020       Post LOCA H2 recom- '   Environmental Qualification. Move H2 recombiner power           M-1-2-84-124 completed, biner power cabinet                                   cabinet to A milder environement.
Environmental Qualification. Move H2 recombiner power M-1-2-84-124 completed, biner power cabinet cabinet to A milder environement.
2PLF3J.
2PLF3J.
L39594       Auxiliary Equipment     Bad damper actuator           failed LIS-VE-01.               Sent out actuator for room damper OVE08YB.                                                                   repair.
L39594 Auxiliary Equipment Bad damper actuator failed LIS-VE-01.
L50841       FW Injection test       Misadjusted limit switches. Had full closed indication to       Shimmed the close limit Valve 2821-F0328.                                     501b power, then no indication   switch for proper' cam to at higher power.                 arm actuation and adjusted the open limit switch indicating cans.
Sent out actuator for room damper OVE08YB.
L54106       HCU 02-39               Packing flange stud nuts       Leaking 10-20 DPM from packing. Tightened packing too loose.                                                     flange stud nuts to 5 in.-lbs.
repair.
L54835       "2B" DG Cooling Water Starting relay set so           Pump will not run after         Reset relay to pick pump 2822-C002.         it won't pick up at 120V.     releasing control switch.       up at 100 V and drop out at 87V.
L50841 FW Injection test Misadjusted limit switches. Had full closed indication to Shimmed the close limit Valve 2821-F0328.
L54847       2D INBD MSIV accum.
501b power, then no indication switch for proper' cam to at higher power.
Pressure Switch out of       Alarm up with normal in           Recalibrated pressure Pressure switch,       calibration,                 pressure.                         switch.
arm actuation and adjusted the open limit switch indicating cans.
L54106 HCU 02-39 Packing flange stud nuts Leaking 10-20 DPM from packing. Tightened packing too loose.
flange stud nuts to 5 in.-lbs.
L54835 "2B" DG Cooling Water Starting relay set so Pump will not run after Reset relay to pick pump 2822-C002.
it won't pick up at 120V.
releasing control switch.
up at 100 V and drop out at 87V.
L54847 2D INBD MSIV accum.
Pressure Switch out of Alarm up with normal in Recalibrated pressure Pressure switch, calibration, pressure.
switch.
2821-N561D.
2821-N561D.
L54861       RCIC Pump Suction Gage Gage was 28 lbs. to high,       Indication differential.         Recalibrated the gage.
L54861 RCIC Pump Suction Gage Gage was 28 lbs. to high, Indication differential.
2E51-R002.             out of calibration.
Recalibrated the gage.
L54885       RCIC Steam supply       Burnt out 74 relay.           Valve does not cycle and has     Replaced 74 Relay.
2E51-R002.
motor operated                                       'no' indication.
out of calibration.
L54885 RCIC Steam supply Burnt out 74 relay.
Valve does not cycle and has Replaced 74 Relay.
motor operated
'no' indication.
2E51-F045.
2E51-F045.
L54927       Equalizing Valve       Valve was leaking at the       Failure of LTS-300-2.           Tightened flange.
L54927 Equalizing Valve Valve was leaking at the Failure of LTS-300-2.
on outer door of       flange.
Tightened flange.
on outer door of flange.
personnel access hatch.
personnel access hatch.
DOCUMENT 0044r/0005r
DOCUMENT 0044r/0005r


1 TABLE 1                                                   ', .
1 TABLE 1 CONNECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK RBQUEST COMPONENT
CONNECTIVE MAINTENANCE OF                                     '
.CAUSE OF MALFUNCTION RESULTS AND EFFECTS
SAFETY RELATED EQUIPMENT WORK RBQUEST   COMPONENT             .CAUSE OF MALFUNCTION           RESULTS AND EFFECTS       . CORRECTIVE ACTION ON SAFE PLANT OPERATION L54933       RCIC Water Leg Pump   Bad Pump and Coupling.     Pump trips on breaker,thermals Replaced pump and 2E51-C003.                                         after starting. .             coupling.
. CORRECTIVE ACTION ON SAFE PLANT OPERATION L54933 RCIC Water Leg Pump Bad Pump and Coupling.
L54951       "B" VC Train Chlorine Loose Recepticle connector Detector tripped but won't       Rinsed electrode with detector 0AE-VC091B. on electrode unit and       ' reset.                       D.I. water and reset trip..
Pump trips on breaker,thermals Replaced pump and 2E51-C003.
after starting..
coupling.
L54951 "B" VC Train Chlorine Loose Recepticle connector Detector tripped but won't Rinsed electrode with detector 0AE-VC091B.
on electrode unit and
' reset.
D.I. water and reset trip..
dirty electrode.
dirty electrode.
L54985       Suppression Pool     Chart drum was loose.       Drive spool was inoperable. Tightened drum.
L54985 Suppression Pool Chart drum was loose.
Drive spool was inoperable.
Tightened drum.
Temperature recorder 2TR-CM037.
Temperature recorder 2TR-CM037.
E5171       D/W and Supp. Pool     Inconsistent output from   Point #6 Reads Hi.             Replaced. controller, recorder 2TR-CM037. love controller.
E5171 D/W and Supp. Pool Inconsistent output from Point #6 Reads Hi.
E5380       Suppression Pool       Misadjusted clutch         The printer was typing but not Tightened clutch-Temperature Recorder   assembly,                   driving.                     assembly.
Replaced. controller, recorder 2TR-CM037.
love controller.
E5380 Suppression Pool Misadjusted clutch The printer was typing but not Tightened clutch-Temperature Recorder
: assembly, driving.
assembly.
2TR-CM038.
2TR-CM038.
L55554       HCU 05-15 Drain Valve Leakage past cartridge       Loss of pressure to HCU.     Installed new 2Cll-111.             valve.                                                     cartridge valve.
L55554 HCU 05-15 Drain Valve Leakage past cartridge Loss of pressure to HCU.
L55674       APRM "C" 2C51-K605. Failed Power Supply         Inoperable APRM C string. Replace power supplies.
Installed new 2Cll-111.
valve.
cartridge valve.
L55674 APRM "C" 2C51-K605.
Failed Power Supply Inoperable APRM C string.
Replace power supplies.
1 DOCUMENT 0044r/0005r
1 DOCUMENT 0044r/0005r


l
' C.
      , ' C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, January 1 through January 31, 1986. This information is provided
LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, January 1 through January 31, 1986. This information is provided Pursuant to the reportable occurrence reporting requirements as set forth in 10CPR 50.~13.
.        Pursuant to the reportable occurrence reporting requirements as set forth in 10CPR 50.~13.
Licensee Event ReDort Number Date Title of occurrence 85-048-00 12/24/85 Trip of RCIC Water Leg Pump Due to Breaker Thermals that would not reset.
Licensee Event ReDort Number                 Date Title of occurrence 85-048-00                             12/24/85 Trip of RCIC Water Leg Pump Due to Breaker Thermals that would not reset.
l DOCUMENT ID 0036r/0005r
l DOCUMENT ID 0036r/0005r


        . D. DATA TABULATIOblS                                                                                                                   .
. D.
The following data tabulations are presented in this report:
DATA TABULATIOblS The following data tabulations are presented in this report:
: 1. Operating Data Report
: 1. Operating Data Report
: 2. Average Daily Unit Power Level
: 2. Average Daily Unit Power Level
: 3. Unit shutdowns and Power Reductions 3
: 3. Unit shutdowns and Power Reductions 3
d DOCUMIDIT ID 0036r/0005r
d DOCUMIDIT ID 0036r/0005r
 
* 1. OPERATING DATA REPORT DOCKET NO. 050-374 9
      *1. OPERATING DATA REPORT 9                                                            DOCKET NO. 050-374 UNIT LaSalle Two 4                                                                            DATE February 7, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
UNIT LaSalle Two DATE February 7, 1986 4
: l. REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744
COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS l.
: 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036   DESIGN ELECTRICAL RATING (MWe-Net): 1078
REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744 2.
: 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):                 N/A
CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 3.
: 4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE           CUMULATIVE 5     NUMBER OF HOURS REACTOR WAS CRITICAL       744                 744         6133.4
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
: 6. REACTOR RESERVE SHUTDOWN HOURS             0.0                 0.0         1687.1
N/A 4.
: 7. HOURS GENERATOR ON LINE                   744                 744         5980.3
REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5
: 8. UNIT RESERVE SHUTDOWN HOURS               0.0                 0.0           0.0
NUMBER OF HOURS REACTOR WAS CRITICAL 744 744 6133.4 6.
: 9. GROSS THERMAL ENERGY GENERATED (MWH) 2166024           2166024           17674576
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1687.1 7.
: 10. GROSS ELEC. ENERGY GENERATED (MWH)       724781       724781             5834850
HOURS GENERATOR ON LINE 744 744 5980.3 8.
: 11. NET ELEC. ENERGY GENERATED (MWH)         707010       707010             5530225
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.
: 12. REACTOR SERVICE FACTOR                       100%                 100%         54.3%
GROSS THERMAL ENERGY GENERATED (MWH) 2166024 2166024 17674576 10.
: 13. REACTOR AVAILABILITY FACTOR                 100%                 100%         69.2%
GROSS ELEC. ENERGY GENERATED (MWH) 724781 724781 5834850 11.
: 14. . UNIT SERVICE FACTOR                       100%                 100%         52.9%
NET ELEC. ENERGY GENERATED (MWH) 707010 707010 5530225 12.
: 15. UNIT AVAILABILITY FACTOR                     100%                 100%         52.9%
REACTOR SERVICE FACTOR 100%
: 16. UNIT CAPACITY FACTOR (USING MDC)             91.7%               91.7 L       29.2%
100%
: 17. UNIT CAPACITY FACTOR (USING DESIGN MWe)                                     88.2%               88.2%       28.0%
54.3%
: 18. UNIT FORCED OUTAGE RATE                   0.0%               0.0%       24.3%
13.
: 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
REACTOR AVAILABILITY FACTOR 100%
100%
69.2%
: 14.. UNIT SERVICE FACTOR 100%
100%
52.9%
15.
UNIT AVAILABILITY FACTOR 100%
100%
52.9%
16.
UNIT CAPACITY FACTOR (USING MDC) 91.7%
91.7 L 29.2%
17.
UNIT CAPACITY FACTOR (USING DESIGN MWe) 88.2%
88.2%
28.0%
18.
UNIT FORCED OUTAGE RATE 0.0%
0.0%
24.3%
19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
There are no shutdowns scheduled over the next 6 months.
There are no shutdowns scheduled over the next 6 months.
: 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A DOCUMENT ID 0036r/0005r
20.
: 2. AVERAGE DAILY UNIT POWER LEVEL
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A DOCUMENT ID 0036r/0005r
    '                                                  DOCKET NO: 050-374
: 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374
~,'                                                         UNIT: LASALLE TWO DATE: February 7, 1986 COMPLETED BY: Jasses P. Peters TELEPHONE: (815) 357-6761 MONTH: January DAY AVERAGE DAILY POWER LEVEL         DAY AVERAGE DAILY POWER LEVEL (MWe-Net)                             (MWe-Net)
~,'
: 1.           872                 17.                 1073
UNIT: LASALLE TWO DATE: February 7, 1986 COMPLETED BY: Jasses P. Peters TELEPHONE: (815) 357-6761 MONTH: January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
: 2.           873                 18.                 1076 3           829                 19.                 1073
(MWe-Net) 1.
: 4.           873                 20.                 1055
872 17.
: 5.           878                 21,                 1057
1073 2.
: 6.           876                 22.                 1080
873 18.
: 7.           914                 23.                 1075
1076 3
: 8.           926                 24.                 1071
829 19.
: 9.           989                 25.                 742 10,           936                 26.                 729 11.-         645                 27.                 832
1073 4.
: 12.           856                 28.                 946
873 20.
: 13.           1006                 29.                 1042
1055 5.
: 14.           1000                 30.                 1017
878 21, 1057 6.
: 15.           1048                 31.                 987
876 22.
: 16.           1081 DOCUMENT ID 0036r/0005r
1080 7.
914 23.
1075 8.
926 24.
1071 9.
989 25.
742 10, 936 26.
729 11.-
645 27.
832 12.
856 28.
946 13.
1006 29.
1042 14.
1000 30.
1017 15.
1048 31.
987 16.
1081 DOCUMENT ID 0036r/0005r


ATTACHMENT E                                                     ,
ATTACHMENT E 3.
: 3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 050-374 UNIT NAME LaSalle Two DATE February 7, 1986 REPORT MONTH JANUARY 1986                 COMPLETED BY James P. Peters
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 050-374 UNIT NAME LaSalle Two DATE February 7, 1986 REPORT MONTH JANUARY 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE-NO.
!                                                                                                                              TELEPHONE (815)357-6761 METHOD OF TYPE                                                                 SHUTTING DOWN F: FORCED                             DURATION                         THE REACTOR OR       CORRECTIVE-NO.               DATE     S: SCHEDULED                           (HOURS)         REASON           REDUCING POWER       ACTIONS / COP 9 TENTS 13                 1/11/86 F                                     50               B                   5                 Repair Steam Leak.
DATE S: SCHEDULED (HOURS)
i 14                 1/25/86 F                                     30               B                   5                 Troubleshoot bypass valve problem.
REASON REDUCING POWER ACTIONS / COP 9 TENTS 13 1/11/86 F
50 B
5 Repair Steam Leak.
i 14 1/25/86 F
30 B
5 Troubleshoot bypass valve problem.
i DOCUMENT 0044r/0005r
i DOCUMENT 0044r/0005r


, ''  E. UNIQUE REPORTING REQUIREMENTS
E.
: 1. Safety / Relief Valve Operations for Unit Two.
UNIQUE REPORTING REQUIREMENTS 1.
DATE         VALVES         NO & TYPE     PLANT         DESCRIPTION ACTUATED       ACTUATIONS     CONDITION     OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.
Safety / Relief Valve Operations for Unit Two.
DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.
DOCUMENT ID 0036r/0005r
DOCUMENT ID 0036r/0005r
: 2. ECCS SyI;tems Outtgea
 
  ,'            The following outages were taken on ECCS Systems during the reporting period.
2.
OUTAGE NO.         BOUIPtGDIT                   PURPOSE OF OUTAGE 2-16-86             "2A" RHR Service Water Pump   Replace Motor.
ECCS SyI;tems Outtgea The following outages were taken on ECCS Systems during the reporting period.
2-20-86             2DG08CB                       Replace Gasket.
OUTAGE NO.
2-50-86             2E12-C300A                   Lube Coupling 2-52-86             2E12-F064C                   Keep Valves Closed.
BOUIPtGDIT PURPOSE OF OUTAGE 2-16-86 "2A" RHR Service Water Pump Replace Motor.
2-20-86 2DG08CB Replace Gasket.
2-50-86 2E12-C300A Lube Coupling 2-52-86 2E12-F064C Keep Valves Closed.
DOCUMENT ID 0036r/0005r
DOCUMENT ID 0036r/0005r
: 3. Off-Sits Dos 3 Calculstion Manual
 
    .;e o'         There were no changes to the ODCM during this reporting period.
3.
: 4. Radioactive Waste Treatment Systems.
Off-Sits Dos 3 Calculstion Manual
.;e o'
There were no changes to the ODCM during this reporting period.
4.
Radioactive Waste Treatment Systems.
There were no changes to the radioactive waste treatment system during this reporting period.
There were no changes to the radioactive waste treatment system during this reporting period.
i l
i l
Line 404: Line 616:
I l
I l
I l
I l
l       DOCUMENT ID 0036r/0005r
l DOCUMENT ID 0036r/0005r


Commonw;:lth Edison           '
Commonw;:lth Edison c
c        LaSalle County Nuclear station RuralRoute #1, Box 220 f,/          --
LaSalle County Nuclear station f,/
V;       Marseilles, Illinois 61341 v                     Telephone 815/357-6761 February 7, 1986 Director, Office of Management Information and Prograsa Control United States Nuclear Regulatory Coussission Washington, D.C.       20555 ATTW: Document Control Desk Gentlemen:
RuralRoute #1, Box 220 V;
Marseilles, Illinois 61341 v
Telephone 815/357-6761 February 7, 1986 Director, Office of Management Information and Prograsa Control United States Nuclear Regulatory Coussission Washington, D.C.
20555 ATTW: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering-LaSalle County Nuclear Power Station for the period January 1, 1986 through January 31, 1986.
Enclosed for your information is the monthly performance report covering-LaSalle County Nuclear Power Station for the period January 1, 1986 through January 31, 1986.
Very truly yours,
Very truly yours, l
                                                            , l      u
u
                                                          'G   J. Diederich Station Manager LaSalle County Station GJD/RJR/cth Enclosure l     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, CBCo INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident-H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle i
'G J. Diederich Station Manager LaSalle County Station GJD/RJR/cth Enclosure l
Document 0043r/0005r                                                           I
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, CBCo INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident-H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle i
Document 0043r/0005r I
. -...}}

Latest revision as of 03:15, 11 December 2024

Monthly Operating Repts for Jan 1986
ML20153B670
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/31/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8602140374
Download: ML20153B670 (32)
v • d • e


Text

,

.6 n'

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JANUARY, 1986 CONT 0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. WPF-11 Doctament 0043r/0005r kk2I4hg lh373 R

PM

5 I.

INTRODUCTION 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 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 Edision Company.

Unit one was issued operating license number NPF-1L 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 James P. Peters, telephone number (815)357-6761 extension 325.

J.

Document 0043r/0005r

T:

TABLE OF CONTENTS s.

1.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Summary of Operating Experience B.

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

Asaendiments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Experiinents Requiring NRC Approval 4.

Corrective Maintenance of Safety Related Equipement 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 Steasa Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

itajor Changes to Radioactive Waste Treatement System l

l Document 0043r/0005r

-,,--..,n-

,,-,,-,,--.---,-~_.--,,,,.,,-,rn---,-,.-,-,w,--,a,~,-w,,,___r,

,,,.,,,-n.,-wgr--n,---,,-,--,,,,

1 s

-II.

MONTHLY REPORT FOR UNIT ONE A.

SUlWUutY OF OPERATING EXPERIENCE FOR UNIT ONE January 1-31 Jan. 1, 0001 Hours.

The Unit entered January with the reactor subcritical and g

unit-off line in cold shutdown for first refuel outage.

Jan. 31, 2400 Hours.

Reactor in cold shutdown for

.Eirst refueling outage.

1 4

4

}

i Document 0043r/0005r

. ~ _. _ _ _ _ _..

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

- MAINTENANCE.

1.

Amendments to facility license or Technical Specification.

Amendment 32-This revised Unit #1 Technical Speciafication to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.

2.

Facility or procedure changes requiring NRC approval.

There were no Facility or Procedure Changes Requiring NRC approval during this reporting period.

3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during this reporting period.

4.

Corrective maintenance of safety related equipment.

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 number, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

Document 0043r/0005r

R TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED'BQUIPMENT WORK REQUEST 00ffCNENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L20781 Prelube Pump for "0"

Per Tech. Spec. 3.8.1.1/2 Preclude. dry-starting of M-1-0-83-026 completed.

DG, ODG0lK Diesel Engine.

L20784 Prelube pump for "lB" Per Tech. Spec. 3.8.1.1/2 Preclude dry-starting of M-1-1-82-319 completed.

DG, IDG02K.

Diesel Engine.

L20786 Controls and Instr.

Per Tech. Spec. 3.8.1.1/2 Mount on vibration free floor M-1-0-82-132 completed.

for ODG, ODGOIK.

or vibration mounts.

L20788 Controls and Instr.

Per Tech. Spec. 3.8.1.1/2 Mount on vibration free floor M-1-1-82-309 completed.

for "lB" DG, IDG02K.

or vibration mounts.

L38021 Post LOCA H2 recom-Envionmental Qualification. Move H2 recombiner power M-1-1-84-079 completed, biner power cabinet cabinet to a milder environment.

IPLF3J.

L52734 "0" DG Cooling Water Packing Leak at valve.

No potential effect.

Repacked valve.

upstream stop ODG006.

L54555 Mechanical Snubber Bad snt.bber.

Failed LTS-500-14.

Replaced snubber.

MsC6-10165.

L54641 "1B" DG Panel Wire lar.ied on wrong No potential effect.

Wired per drawing IE22-P301B.

terminal block.

Due to M-1-1-82-319.

in modification.

L54682 "1B" HPCS Diesel Wire landed on wrong No potential effect, Wired per drawing IE22-F301B.

terminal block.

Due to M-1-1-82-319.

in modification.

L54912 LPRM 6A-32-09 Downscale light on full False downscale indications.

Replaced transister APRM F core display would not on circuit card.

clear in bypass.

L54913 LPRM 1A-16-57 Drifting upscale and No potential effect, full Replaced upscale and APRM-F.

Downscale points.

core display worked properly.

downscale comparator.

DOCUMENT 0044r/0005r

i TABLE 1 CORRECTIVE MAINTENANCE OF

~

SAFETY RELATED BQUIPfEENT WORK REQUEST C0ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION s

L54914 LPRM 56-48-17 The downscale light on full Failure of applicable portions-- Repaired circuit card.

LPRM A core display would not of LIS-NR-ll6.

energize.

t L54D15

.LPRM SC-48-25 Bad lamp and no divider No potential effect, all lights Installed light divider APRM B

.between SC-48-25 and on back panel worked.

and replaced lamp.

5D-48-25.

l L54916 LPRM 5A-40-25 Poor solder connection on Sporadic light indication.

Resoldered bad APRM E circuit board, connection on circuit.

board.

1 L54975 Fuel Oil transfer Blind Flange orifice LTS-1000-24 satisfactorily.

Replaced orifice plate.

pump recirc. orifice plate for LTS-1000-24.

Plate OD08M.

L55129 "0" DG Pressure Switch OPSL-DG046/50. piped off No. potential effect, per Repiped pressure switches.

j piping ODG0lK.

discharge of oil pump, per M-1-0-83-026.

should be piped to turbo charger.

?

L55132 Chlorine detector Dirty Detector Tank and Failed LIS-VC-01.

Cleaned detector tank oAE-VC-090A.

bad wick.

and. replaced wick.

1 L55371 containment Monitor Toe large of deviation be-Indecision in indication, Replaced ITI-CM040.

ITR-CM037/40.

tween ITR-CM037 and failed LIP-RX-02.

ITR-CM040.

L55405

Replaced thermal breaker 7A.

bed.

overload relay.

L55582 Control Room HVAC Dirt on clogged oil filter. HVAC unit keeps tripping on Cleaned out filter.

OVC04CA.

Iow oil pressure.

i DOCUMENT 0044r/0005r

l C.

LICENSEE EVENT REPORTS l

The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, January 1 through January 31, 1986. This inforination is provided pursuant to the reportable occurrence reporting requireinents as set forth in 10CFR 50.73.

Licensee Event ReDort MUInber Date Title of Occurrence There were no licensee event reports in this reporting period.

Docusment 0043r/0005r

4 D.

DATA TABULATIODIS 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 J

Doctament 0043r/0005r

1.

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE February 7, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):]R1 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 3.

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

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

N/A THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 12039.00 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.00 7.

HOURS GENERATOR ON LINE 0.0 0.0 11642.00 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 32213650

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 10499394
11. NET ELEC. ENERGY GENERATED (MWH)

-5582

-5582 9998875

12. REACTOR SERVICE FACTOR 0.0%

0.0%

65.7%

13. REACTOR AVAILABILITY FACTOR 0.0%

0.0%

74.7%

14. UNIT SERVICE FACTOR 0.0%

0.0%

63.6%

15.

UNIT AVAILABILITY FACTOR 0.0%

0.0%

63.6%

16.

UNIT CAPACITY FACTOR (USING MDC)

-0.72%

-0.72%

52.7%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe)

-0.69%

-0.69%

50.6%

18. UNIT FORCED OUTAGE RATE 0.0%

0.0%

17.4%

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

The First Refueling Maintenance, surveillance and Modification Outage began October 18, 1985 and will last 30 weeks.

20.

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

May, 1986 Document 0043r/0005r

f

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: February 7. 1986 COMPLETED BY: Jenes P. Peters TELEPHONE: (815) 357-6761 MONTH: JANUARY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met)

(MWe-Net) 1.

-5 17.

-6 2.

-5 18.

-8 3

-6 19.

-5 4.

-7 20.

-5 5.

-4 21.

-5 6.

-4 22.

-12

't.

-3 23.

-13 8.

-4 24.

-14 9.

-4 25.

-13 10.

-4 26.

-14 11.

-5 27.

-14 12.

-3 28.

-14 13.

-4 29.

-14 14.

-4 30.

-13 15.

-4 31.

-13 16.

-3 Document 0043r/0005r

a ATTACIDENT E 3.

UNIT SHUTDOWS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAM LaSalle One DATE FEBRUARY 7.

1986 REPORT MONTH JANUARY 1986 COfFLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S:. SCHEDULED (HOURS)

REASON REDUCING POWBd ACTIONS /COf9EENTS There were no Unit shutdowns or power reductions during this reporting period.

i~

i i

f

~

m m

~

~

a As DOCUMENT 0044r/0005r

E.

UNIQUE REPORTING REQUIREMIDITS

\\

1. Safety / Relief valva operations for Unit One.

' VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety R911ef Valves Operated for Unit One during this reporting period.

J

~

1

\\

s e

1 1

4 i,

s i

i Doctament 0043r/0005r t

s 2.

ECCS Systems Outrge3 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE 0-8-86 "0"D/G Calibration of speed tachometer 0-24-86 Security D/G Annual Inspection 1-2-86 "0"D/G Fuel Oil Transfer Change orifice Pump 1-4-86 1E12-F021 LES-BQ-112 1-5-86 IE12-F042C LES-BQ-112 1-6-86 1812-F042C 1E12-F327C 1-7-86 1E12-F042C Worm Gear Inspection 1-8-86 "0" D/G Recondition Air Start Motors 1-14-86 1E51-F066 Repair Position Indicator 1-29-86 "A" RHR System Replace Pump Shaft 1-33-86 1821-F001 LES-BQ-112 1-35-86 SDC Line Repair 1812-F008/9 1-36-86 1E22-F011 LES-BQ-112 1-37-86 1822-F015 LES-BQ-112 1-38-86 1E22-F001 LES-BQ-ll2 1-39-86 1E12-F009 LES-BQ-112 1-40-86 1E12-F008 LES-BQ-112 1-41-86 IE12-F006A LES-BQ-112 1-42-86 1E12-F006B LES-BQ-112 1-43-86 1E51-F063 Repack Valve 1-44-86 IE21-F001 Remove Limitorque 1-49-86 "C" RHR Replace Puffer Piston 1-50-86 IE12-F004A Change Grease 1-51-86 1E12-F016A Repair Valve 1-52-86 IE12-F024B Repack Valve 1-53-86 IE12-F020 Prevent Drawing Vessel 1-54-86 1E12-F064A Repack Valve 1-55-86 1812-F064A LES-BQ-il2 1-56-86 1E12-F004A LES-BQ-112 1-57-86 1E12-F312A LES-BQ-112 1-58-86 1812-F312B LES-BQ-112 1-59-86 143-1 Feed Breaker Inspect Breaker 1-62-86 IB D/G Repair Air Start Motor 1-63-86 1E22-5003 Inspect Breaker 1-64-86 RCIC Replace Drain Pot Level Instrument Isolation Valves 1-65-86 "1B" RHR HX Service Hydrolaze HX water Side 1-66-86 LE12-F046C Inspection 1-67-86 lE12-F003A LES-BQ-112 1-68-86 1E12-F016A LES-BQ-112 1-69-86 1E12-F023 LES-BQ-112 1-70-86 1E12-F024A LES-BQ-112 Document 0043r/0005r

CUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE 1-71-86 1E12-F027A LES-Bg-112 1-72-86 1E12-F040A-LES-BQ-112 1-73-86 1E12-F047A LES-Bg-112 1-74-86 1E12-PO48A LES-BQ-112 1-75-86 1812-F053A LES-BD-112 1-76-86 1E12-F099A LES-Bg-112 1-77-86 1DG035 Flush Gear Casing 1-19-86 IE12-F024A Repack Valve 1-81-86 "1B"D/G Breaker 143-3 Inspect Breaker 1-82-86 "1B" D/G Replace Diode 1-89-86 1E12-F327A Remove Testable Check Valve 1~91-86 LE12-PO41A Repair Testable Check 1-92-86 IE12-F063B Fill "B" RHR

'(

1-93-86 1821-F041C Fix Actuator 1-97-86 1812-F063B Keep "B" RHR Filled 1-108 1812-F003B LES-BQ-112 1-109-86 1812-F040B

-LES-BQ-112 1-110-86 1812-F064B LES-BQ-112 1-111-86 1E12-F094 LES-BO-112 1-114-86 "1B" RHR Pump Replace Puffer Piston 1-115-86 "1B" RHR Pump LES-EQ-112 1-116-86 1E12-F004B LES-BQ-112 1-117-86 1812-F017B LES-BQ-112 1-118-86 1812-F024B LES-ag-112 1-119-86 1812-F027B LES-Bg-112 i

\\

1-120-86 1812-F042B LES-Bg-112 1-121-86 1E12-F047B LES-BQ-112 l

1-122-86 1E12-F048B LES-BQ-112 1-123-86 1E12-F053B LES-BQ-112 1-124-86 IE12-F099B LES-BQ-112 1-129-86 1812-F402B Locked Valve Tracking 1-132-86 "1A" D/G Prelube; Modification 1-133 "1A" D/G Protective Relay Calibrations 1-134-86 "1A" D/G Replace Pressure Switch 1-135-86 "1A" D/G Replace Puffer Piston

'l-137-86 1851-N009A/9B/12A-D/20 E.Q. Switch Replace 1-159-86 1812-F099B Remove Valve.

1-160-86 1812-F026B Replace Handwheel 1-162-86 "B" RHR Service Water Install Isolation Valves 1-163-86 HPCS M-1-1-82-292 1-166-86 1821-N005 Revise Switch Logic 1-167-86 1E12-F046A Inspection 4

1-168-86 "1C" RHR Pump Change Oil 1-169-86 HPCS Pump Change Oil 1-173-86 "B" RHR Service Water Repack Valve Strainer 1-174-86 1812-F050A Repack Valve 1-175-86 IE12-F042B Inspect Operator 1-177-86 1E22-N001A/B E.Q. Switch Replace 1-178-86 1851-N010 -

E.Q. Switch Replace 1-179-86 LE22-N002A/B E.Q. Switch Replace 1-180-86 IE51-NO35A/E E.Q. Switch Replace Document 0043r/0005r

~

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

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 1-184-86 1812-F0463 Inspection 1-187-86 1812-F312A Rotate Liinitorque 1-188-86 1E12-F011B Reinstall Handwheel j

1-189-86 1DG01P Inspect Motor

~

1-191-86 1E22-F015 Rotate Operator 1-196-86_

1812-F041B Rebuild Operator i

1-198-86 1851-N002A E.Q. Mod 1-199-86 IE12-F026B Handwheel Problem 1-200-86 1E12-F027B Remove Screw 1-201-86 1E12-F027A Rotate Limitorque 1-203-86 1E21-F012 LTS-600-3 1-208-86 "B" RHR Change Motor Oil 1-211-86 "1A" D/G Fuel Oil Remove Orifice xfer Pump Document 0043r/0005r

3 Off-Sito Dose Calculition Manual There were no changes to the ODCM during this reporting period.

4.

Radioactive Waste Treatment Systems.

There were no significant changes to the radioactive waste treatment system during this reporting period.

t i

l l

Document 0043r/0005r

i 4

LASPLLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT i

JANUARY 1986 COttt0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF--18 i

t f

I i

t l'

DOCUh3NT ID 0036t/0005r

-_.___. _ _ _ _ - _ -. ~..,.. _..

I.

INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Cosumonwealth Edison Company and located near Marseilles, 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, i

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 James P. Peters, telephone number (815)357-6761 extension 325.

M i

DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS 1.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

Summary of Operating Experience B.

PLANT OR 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 REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System I

DOCUMENT ID 0036r/0005r

. ~ _, _ _ _ -.

II.

MONTHLY REPORT FOR UNIT TWO

  • A.

SUtetARY OF OPERATING EXPERIENCE FOR UNIT TWO January 1-31 Jan. 1, 0001 Hours.

The Unit entered January with the reactor critical at 88% power and generator on-line at 886 MWe.

Jan. 3, 1405 Hours.

"A" TDRFP tripped and power dropped to 53% (592 MWe).

Jan. 3, 2300 Hours.

Power recovered to 89% (890 MWe) and limited due to work in the heater bay.

Jan. 9, 1400 Hours.

Reactor Power increased to 97%

(1060 MWe).

Jan. 9. 1430 Hours.

Reactor Power dropped to 92% (1014 MWe) due to RR controller problems.

Jan. 9,

'300 Hours.

Reactor Power restored to 96%

(1050 MWe).

Jan. 10, 0500 Hours. Reactor Power dropped to 93% (1020 MWe) due to heater drain problems.

Jan. 10, 1900 Hours. Reactor Power reduced to 48% (530 MWe) for control rod manipulation.

Jan. 11, 0730 Hours. Reactor Power reduced to 55% (600 MWe) to work on steam leak.

Jan. 13, 1730 Hours. Reactor Power increased to full power at 99% (1081 MWe).

Jan. 14, 1600 Hours. Reactor Power dropped to 87% (951 MWe) for control rod ranipulation.

Jan. 15, 1200 Hours. Reactor Power increased to full power at 99% (1100 MWe).

Jan. 17, 0125 Hours. Reactor Power reduced to 96% (1050 MWe) for control rod manipulations.

Jan. 17, 1500 Hours. Reactor Power increased to and holding at 100% (1115 MWe).

Jan. 20, 2025 Hours. Reactor Power reduced to 86% (958 MWe) for control rod manipulation.

Jan. 21, 1200 Hours. Reactor Power restored to full power at 100% (1110 MWe).

Jan. 25, 0700 Hours. Reactor Power reduced to 75% (840 MWe) for surveillance testing.

Jan. 25, 1040 Hours. Reactor Power reduced to 17% (224 MWe) due to bypass valve problem.

Jan. 27, 0700 Hours. Reactor Power restored to 82% (920 MWe).

Jan. 27, 1120 Hours. Reactor Power reduced to 64% (719 MWe) for survie11ance testing, i

Jan. 29, 2000 Hours. Reactor Power increased to full power at 99% (1080 MWe).

l Jan. 30, 2100 Hours. Reactor Power reduced to 80% (900 MWe) for control rod manipulation.

Jan. 31, 2400 Hours. Reactor Power at full power at 100% (1118 MWe).

I DOCUMENT ID 0036r/0005r

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

1.

Amendments to facility license or Technical Specification.

Amendment 18-This revised Unit 2 Technical Specification to allow up to four fuel bundles to be loaded around each source range monitor with no minimum channel count rate requirements.

4 2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure change 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.

4.

Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of safety-related maintenance completed.on Unit Two during tha reporting period. The headings indicated in this susmaary include: Nork Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

DOCUMENT ID 0036r/0005r

, _,. _ _. ~

TABLE 1 CORRECTIVE MAINTENANCE OF 2

SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L38020 Post LOCA H2 recom- '

Environmental Qualification. Move H2 recombiner power M-1-2-84-124 completed, biner power cabinet cabinet to A milder environement.

2PLF3J.

L39594 Auxiliary Equipment Bad damper actuator failed LIS-VE-01.

Sent out actuator for room damper OVE08YB.

repair.

L50841 FW Injection test Misadjusted limit switches. Had full closed indication to Shimmed the close limit Valve 2821-F0328.

501b power, then no indication switch for proper' cam to at higher power.

arm actuation and adjusted the open limit switch indicating cans.

L54106 HCU 02-39 Packing flange stud nuts Leaking 10-20 DPM from packing. Tightened packing too loose.

flange stud nuts to 5 in.-lbs.

L54835 "2B" DG Cooling Water Starting relay set so Pump will not run after Reset relay to pick pump 2822-C002.

it won't pick up at 120V.

releasing control switch.

up at 100 V and drop out at 87V.

L54847 2D INBD MSIV accum.

Pressure Switch out of Alarm up with normal in Recalibrated pressure Pressure switch, calibration, pressure.

switch.

2821-N561D.

L54861 RCIC Pump Suction Gage Gage was 28 lbs. to high, Indication differential.

Recalibrated the gage.

2E51-R002.

out of calibration.

L54885 RCIC Steam supply Burnt out 74 relay.

Valve does not cycle and has Replaced 74 Relay.

motor operated

'no' indication.

2E51-F045.

L54927 Equalizing Valve Valve was leaking at the Failure of LTS-300-2.

Tightened flange.

on outer door of flange.

personnel access hatch.

DOCUMENT 0044r/0005r

1 TABLE 1 CONNECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK RBQUEST COMPONENT

.CAUSE OF MALFUNCTION RESULTS AND EFFECTS

. CORRECTIVE ACTION ON SAFE PLANT OPERATION L54933 RCIC Water Leg Pump Bad Pump and Coupling.

Pump trips on breaker,thermals Replaced pump and 2E51-C003.

after starting..

coupling.

L54951 "B" VC Train Chlorine Loose Recepticle connector Detector tripped but won't Rinsed electrode with detector 0AE-VC091B.

on electrode unit and

' reset.

D.I. water and reset trip..

dirty electrode.

L54985 Suppression Pool Chart drum was loose.

Drive spool was inoperable.

Tightened drum.

Temperature recorder 2TR-CM037.

E5171 D/W and Supp. Pool Inconsistent output from Point #6 Reads Hi.

Replaced. controller, recorder 2TR-CM037.

love controller.

E5380 Suppression Pool Misadjusted clutch The printer was typing but not Tightened clutch-Temperature Recorder

assembly, driving.

assembly.

2TR-CM038.

L55554 HCU 05-15 Drain Valve Leakage past cartridge Loss of pressure to HCU.

Installed new 2Cll-111.

valve.

cartridge valve.

L55674 APRM "C" 2C51-K605.

Failed Power Supply Inoperable APRM C string.

Replace power supplies.

1 DOCUMENT 0044r/0005r

' C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, January 1 through January 31, 1986. This information is provided Pursuant to the reportable occurrence reporting requirements as set forth in 10CPR 50.~13.

Licensee Event ReDort Number Date Title of occurrence 85-048-00 12/24/85 Trip of RCIC Water Leg Pump Due to Breaker Thermals that would not reset.

l DOCUMENT ID 0036r/0005r

. D.

DATA TABULATIOblS 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 3

d DOCUMIDIT ID 0036r/0005r

  • 1. OPERATING DATA REPORT DOCKET NO. 050-374 9

UNIT LaSalle Two DATE February 7, 1986 4

COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS l.

REPORTING PERIOD: December 1985 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): N/A THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 744 744 6133.4 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1687.1 7.

HOURS GENERATOR ON LINE 744 744 5980.3 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2166024 2166024 17674576 10.

GROSS ELEC. ENERGY GENERATED (MWH) 724781 724781 5834850 11.

NET ELEC. ENERGY GENERATED (MWH) 707010 707010 5530225 12.

REACTOR SERVICE FACTOR 100%

100%

54.3%

13.

REACTOR AVAILABILITY FACTOR 100%

100%

69.2%

14.. UNIT SERVICE FACTOR 100%

100%

52.9%

15.

UNIT AVAILABILITY FACTOR 100%

100%

52.9%

16.

UNIT CAPACITY FACTOR (USING MDC) 91.7%

91.7 L 29.2%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 88.2%

88.2%

28.0%

18.

UNIT FORCED OUTAGE RATE 0.0%

0.0%

24.3%

19.

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

There are no shutdowns scheduled over the next 6 months.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A DOCUMENT ID 0036r/0005r

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374

~,'

UNIT: LASALLE TWO DATE: February 7, 1986 COMPLETED BY: Jasses P. Peters TELEPHONE: (815) 357-6761 MONTH: January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

872 17.

1073 2.

873 18.

1076 3

829 19.

1073 4.

873 20.

1055 5.

878 21, 1057 6.

876 22.

1080 7.

914 23.

1075 8.

926 24.

1071 9.

989 25.

742 10, 936 26.

729 11.-

645 27.

832 12.

856 28.

946 13.

1006 29.

1042 14.

1000 30.

1017 15.

1048 31.

987 16.

1081 DOCUMENT ID 0036r/0005r

ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 050-374 UNIT NAME LaSalle Two DATE February 7, 1986 REPORT MONTH JANUARY 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE-NO.

DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS / COP 9 TENTS 13 1/11/86 F

50 B

5 Repair Steam Leak.

i 14 1/25/86 F

30 B

5 Troubleshoot bypass valve problem.

i DOCUMENT 0044r/0005r

E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.

DOCUMENT ID 0036r/0005r

2.

ECCS SyI;tems Outtgea The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

BOUIPtGDIT PURPOSE OF OUTAGE 2-16-86 "2A" RHR Service Water Pump Replace Motor.

2-20-86 2DG08CB Replace Gasket.

2-50-86 2E12-C300A Lube Coupling 2-52-86 2E12-F064C Keep Valves Closed.

DOCUMENT ID 0036r/0005r

3.

Off-Sits Dos 3 Calculstion Manual

.;e o'

There were no changes to the ODCM during this reporting period.

4.

Radioactive Waste Treatment Systems.

There were no changes to the radioactive waste treatment system during this reporting period.

i l

I i

I l

I l

l DOCUMENT ID 0036r/0005r

Commonw;:lth Edison c

LaSalle County Nuclear station f,/

RuralRoute #1, Box 220 V;

Marseilles, Illinois 61341 v

Telephone 815/357-6761 February 7, 1986 Director, Office of Management Information and Prograsa Control United States Nuclear Regulatory Coussission Washington, D.C.

20555 ATTW: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering-LaSalle County Nuclear Power Station for the period January 1, 1986 through January 31, 1986.

Very truly yours, l

u

'G J. Diederich Station Manager LaSalle County Station GJD/RJR/cth Enclosure l

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, CBCo INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident-H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle i

Document 0043r/0005r I

. -...

Retrieved from "https://kanterella.com/w/index.php?title=ML20153B670&oldid=4147580"