ML20236E164
| ML20236E164 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/28/1989 |
| From: | Diederich G, Thunstedt J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8903230475 | |
| Download: ML20236E164 (23) | |
Text
-
- .6 l .
L. . , . g .. ,- ,
.i s 1 t.-
LASALLE NUCLEAR POWER STATION .,
UNIT 1 MONTHLY PERFORMANCE REPORT FEBRUARY 1969 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11' 8903230475 890228 ,.
l PDR ADOCK 05000373 0 R. PNU ac ., - d, (- f)(" .. i
\f I DOCUMENT ID 0043r/0031r 4 I .
. __:___ _._______________z--_-_---_---___--._- - .-
1 I
l TABLE OF CONTENTS l
I. INTRODUCTION I
II. REPORT 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. Changes to procedures which are described in the Safety Analysis Report
- 3. Tests and Experiments not covered in the Safety Analysis Report
- 4. Corrective Maintenance of Safety-Related Equipment
- 5. Completed Safety-Related Modifications j C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level i
- 3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
- 1. Main Steam Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Waste Treatment System ,
- 5. Indications of Failed Fuel Elements {
l i
l l
DOCUMENT ID 0043r/0031r
4 e
I. INTRODUCTION The LaSalle County Nuclear Po,er Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of )
1078 Megawatts. Waste heat is rejected to a man-made cooling pond using i the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company. R
'I Unit One was issued operating license number NPF-11 on April 17, 1982. !
Initial criticality was achieved on June 21, 1982 and commercial power !
operation.was commenced on January 1, 1984.
This report was complied by John W. Thunstedt, telephone number (815)357-6761, extension 2463.
l l
i l
l I
i l
l I
I i
DOCUMENT ID 0043r/0031r t _
T.. l a ,* .
II. MONTHLY REPORT l I
A.
SUMMARY
OF OPERATING EXPERIENCE t -'
Ray Time Event 1
l 1 0000 Reactor critical, generator on-line, 900 MWE, ]
reducing load for MSIV surveillance. j l
0630 Increasing load to 1140 MWE.
8 0200 Reducing load to 1081 MWE for CRD exercising. )
1 0530 Increasing load to 1140 MWE.
L 26 0230 Reducing load to 990 MWE to follow System load.
i 27 2300 Reducing load to 850 MWE for feed-pump maintenance. J 28 2400 Reactor critical, generator on-line, 900 MWE. H I
1 B. PLANT OR PROCEDURE CHANGES, TESTS,' EXPERIMENTS AND SAFETY RELATED ]
MAINTENANCE.
- 1. Amendments to the Facility License or Technical Specification,
- a. Reduce the minimum staffing for the on-site nuclear safety committee from 4 to 3.
l b. Allow single unit operation while the O D/G is DOS for ;
performance of surveillance. '
- c. Add excess-flow check valves for RVWLIS Primary l Containment isolation system.
- 2. Changes to procedures which are described in the Safety Analysis Report.
(None)
- 3. Tosts and Experiments not described in the Safety Analysis Report. !
I (None)
- 4. Major corrective maintenance to Safety-Related Equipment. [
(See Table 1)
- 5. Completed Safety-Related Modifications.
(None) f DOCUMENT ID 0043r/0031r
E y V a d I l r T e a C R C s E
R d d .
R e e O c r C a i l a p p e e R R N
O )
SI e TT v CA i ER t FE a FP v r
EO t e DT o s NN n n AA o O L d c
_ T SP l -
T u nn E LE o oo C T UF W ni N N S A ( .t A E ES r a
_ N PM R e yc E N ti k e T IU O as
_ l d
_ N Q eo un I rl ai A E BC F 1
M'D E
L E E B V T A I A T T EL N C R O
_ E - I R Y T d R T C r a
O N C EF U o A F B R S L O A l
_ J M o y
A r
_ M F a t O l n e o E R C S
U y y A t t C l l
_ u u
_ a a
_ F F
_ t
- u k
_ T p c
_ N t o
- E 3 u l
_ N 2 O B
_ O 4 )
_ P ) 1G r d r
_ M E / e oo O N - Dk R t
_ C O a i
_ N BA e " n
( Cl r B o A( B " M T
S E
U Q ) )
E 0 1 R R 0 3 E T T 0 8 KB I I 0 1
_ RM N N 7 7
_ OU U U 8 8 WN ( ( L L l l
v ,
4
- C. LICENSEE EVENT REPORTS 1
LER Number Date Rgscription j 89-005-00 02/07/89 30 Day-MSL High Flow Switch failure ') reject ~
limit /SOR switch.
89-006-00 02/08/89 30 Day-Unit 1(2) snubbers failed to be classified as safety related. i 1
89-007-00 02/10/89 30 Day-Unanalyzed condition of VC purge damper -
design 89-008 02/28/89 30 Day-SOR Reactor Water Level Switch > reject ]
limit.
j i
l l
l D. DATA TABULATIONS >
- 1. Operating Data Report (attached)
- 2. Average Daily Unit Power Level (attached)
- 3. Unit Shutdowns and Power Reductions (attached)
DOCUMENT ID 0043r/0031r
- \
6
- 1. OPERATING DATA REPORT DOCKET NO. 050-373 j UNIT LASALLE ONE j DATE MARCH 10, 1989 COMPLETED BY J.W. THUNSTEDT-TELEPHONE (815)-357-6761 !
OPERATINi, STATUS ! i i
- 1. REPORTING PERIOD: FEliRUARY 1989 GROSS HOURS IN REPORTING PERIOD: 672 l
- 2. CURRENTLY AUTHORIZED POWER LEVEL (M t): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net) 1,078 - i 1
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): (NONE)
- 4. (EASONS FOR liESTRICTION (If ANY): (N/A)
REPORTING PERIOD DATA l THIS MONTH YEAR-TD-DATE . CUMULATIVE ;
l l 5. TIME REACTOR CRITICAL (HOURS) 672.0 1,416.0 27,435.3
- 6. TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 1,641.2
- 7. TIME GENERATOR DN-LINE (HOURS) 672.0 1,416.0 26,730.5'
- 8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 1.0 - }
- 9. THERMAL ENERGi GENERATED (MWHi-Gross) 2,194,992 4,579,656 73,358,234 l 1
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 752,504 1,571,009 24,216,763 i
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 723,637 1,510,391 23,085,920 I
- 12. REACTOR SERVICE FACTOR (%) 100.0 100.0 60.6
- 13. REACTOR AVAILABILITY FACTOR (%) 100.0 - 100.0 64.2
- 14. SERVICE FACTOR (Z) 100.0 100.0 59.1
- 15. AVAILABILITY FACTOR (Z) 100.0 100.0 59.1
- 16. CAPACITY FACTOR (USING MDC) (1) 103.9 103.0 49.2
- 17. CAPACITY FACTOR (USING DESIGN MWe) (1) 99.9 98.9 47.3
- 18. FORCED OUTAGE FACTOR (1) 0.0 0.0 11.5
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
(NONE)
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
(N/A) 1
4
~
' DOCKET NO.- 950-373 UNIT LASALLE ONE-
- 2. AVERAGE DAILY UNIT POWER LEVEL (NWe-Net) DATE MARCH 10,1989 E0MPLETED BY J.W. THUNSTEDT TELEPHONE (815)-357-6741 e
REPORT PERIOD: FEBRUARY 1999 DAY POWER- DAY POWER 1 979 17 1,086 2 1,090 18 1,089 3 1,089 19 1,087 4 1,089 20 1,092 5 1,088 21 -1,093 4 1,089 6 22 1,074 -
7 1,089 23 1,093 8 1,083 24 1,097 9 1,091 25 1,096 10 1,088 16. 1,075 11 1,087 27 1,094 12 1,087 28 885 13 1,088 29 14 1,091 30 15 1,073 31 16 1,089 l
L
0 a ,J5 S m 5 S0 1 T u 0 a1 Y8 N p
.L h OE cDE B( E M
M g
n d
ee -
NM rEN EO i ec -
A aTO VC t f n TNMEH I / s a E LP TS e rn KTEPE CN T oe CI TML EO t t ONAOE RI V cn DUDCT RT I ai OC S ea CA M RM
> ODOP T
S DGCG N ONAN 4 5 O HI EI I 9 TTRC T 8 ET U C 9 MUED U 1 HHE D S TR
_ E ,
R Y
_ R R A E U W R O B N P E F O D S N A A H E
_ T R B B
_ S N N O
_ W M D
E T T R U O H P N S E O)
. R I S T TR I
D D
E L
_ DU
_ ED
_ YFS T
FS E
_ T
_ A 1 7 D 2
_ L A
_ I T
YNR LEE RUB
_ AQM EE U YSN 3 4
E. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED JLC'IUATIOtl CONDITION OF EVENT _
(None)
- 2. ECCS System Outages QUIAGE_IlQ EOUIPMENT PURPOSE (Unit 0) 0-48-89 ODG08CA Tighten unloader valve caps.
0-49-89 ODG08CB Tighten unloader valve caps.
0-53-89 ODGOBCA Retighten valve hold down screws.
0-54-89 ODG08CB Retighten valve hold-down screws.
IUNIT 1) 1-25-89 1B D/G Replace PI-1E22-NS30 1-27-89 RCIC Vacuum Pump Check brushes 1-28-89 RCIC Condensate Pump Check brushes 1-46-89 1B D/G Repair air-compressor relief valve.
1-52-89 (RCIC) Repair tubing.
1-53-89 (RCIC) Repair oil differential pressure switch.
1-55-89 1A D/G air-compressor Tighten-unloader valve cap.
1-56-89 1B D/G air-compressor Tighten-unloader valve caps.
1-64-89 1A D/G Replace temperature switch.
1-66-89 1DGOBCA Retighten valve held-down screws.
1-73-89 1DG08CA Retighten valve hold-down screws.
- 3. Off-Site Dose Calculation Manual Changes (None)
- 4. Major changes to Radioactive Waste Treatment Systems.
(None)
- 5. Indications of Failed Fuel Elements (None)
DOCUMENT ID 0043r/0031r
v- ..;
, s' ,
l
.1 I
I
'- t
.#~3 1
l E .
LASALLE NUCLEAR' POWER STATION UNIT 2 :!
MONTHLY PERFORMANCE REPORT FEBRUARY, 1989 COMMONWEALTH EDISON COMPANY l
.1 1
NRC DOCKET NO. 050-374 1
LICENSE NO. NPF-18 ]
.t i
i DOCUMENT ID 0036r/0031r i
_________.____m__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____._.______._.___1. _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ ___z.__ _ m._l i
TABLE OF CONTENTS l l
5 I. INTRODUCTION I I .. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED I
MAINTENANCE .
- 1. Amendments'to Facility License or Technical Specifications
- 2. Changes to procedures which are described in the Safety Analysis Report.
- 3. Tests and Experiments not' covered in the Safety Analysis Report.
- 4. Corrective Maintenance of Safety-Related Equipment 5.. Completed Safety Related Modifications .
C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
- 1. Operating Date Report
- 2. Average Daily Unit Power. Level ~ j
- 3. Unit Shutdowns and Power Reductions l
E. UNIQUE REPO't1'ING REQUIREMENTS l
- 1. Safety / Relief Valve Operations
- 2. ECCS System Outages "
l
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes - to Radioactive Maste Treatment System
- 5. Indications of Failed Fuel Elements DOCUMENT ID 0036r/0031r
I. INTRODUCTION .
i The LaSalle County Nuclear Power Station is.a two-unit facility owned by Commonwealth Edison Company and' located near Marsellies, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of-1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.
Unit Two was issued operating Ilcense 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 John W. Thunstedt, telephone number (815)357-6761 extension 2463.
1 DOCUMENT ID 0036r/0031r
=
l a
l O.
l
. 1
)
II. MONTHLY REPORT l
l A.
SUMMARY
OF OPERATING EXPERIENCE j
- I Day Time Eyent '
1 0000 Reactor subcritical, generator off-line, L1R02 continues.
8 0155 Reactor Critical, L2R02 ends.
10 0530 Generator on-line.
1900 Generator output 200 MWE, holding for scram-time testing.
]
l 12 1400 Generator off-line for overspeed testing. I j 2100 Generator on-line at 275, increasing load <
1 13 1430 Reducing load for reactor-recirc pump testing.
15 0830 Increasing load to 750 MWE.
l l 21 0400 Increasing load to 1100 MWE.
I j 28 2400 Reactor critical, generator on-line 1100 MWE.
B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTEN ANCE.
- 1. Amendments to the Facility License or Technical Specification.
- a. Add excess-flow check-valves for RVWLIS primary l containment isolation system.
- b. Reduce the minimum staffing for the on-site nuclear safety committee from 4 to 3.
- c. Allow single unit operation while the "O" D/G is DOS for performance of surveillance.
- 2. Changes to procedures which are described in the Safety Analysis Report.
(None)
- 3. Tests and Experiments not described in the Safety Analysis Report.
(None) l 4. Major corrective maintenance to Safety-Related Equipment.
See Table 1.
- 5. Completed Safety-Related Modifications.
See Table 2.
A . m t h u n E c r e e V t t m d I i D s e a D D D T w R n l l R R R ,
C s C i e b C C C E
R d d d d d d d d R e e e e e e e e O c c c c c c c c C a a a a a a a a l l l l l l l l p p p p p p p p e e e e e e e e R R R R R R R R N
. t O c s SI e l
_ TT j a
- CA e n
_ ER r r
_ FE e
_ FP d t EO e n n d o i DT e i NN e t t AA c e a n e e e e O L x l c e l l l l T SP e b i m b b b b
_ T a d e a a a a E LE h r n l r r r r
_ C T UF c e i e e e e e N N SA t p p p p p A E ES i o c d o o o o N M R w . n i e n n n n
_ E P N st I t g I I i i I
_ T U O i a a
_ NQ Rm D r m D D D D I Oi R r a R R R R
_ 1 A E Sl C E D C C C C
_ M D '
E
_ L E E T
_ B VA
_ A I L
T T N
- C E O E R-
_ I R Y T n R T C y o y y y
_ O N l i l l l C E F U b t b b b A F e m e a m m m
_ R S L r e r r e e e
_ O A u s u b s s s J M l s l i s s s A i a i v a a a a a M F O f g f g g g g n n n n n
_ E l i l i i i i
. S a l t a l n l t l t l t U n pn n t w pn pn pn ue A r r t o ue ue ue C e ob e o n ob ob ob t c t r k c c c n ns n h n ns ns ns I Ui I T U Ui Ui Ui
_ t
_ n
- e
_ m e
_ e d
_ l a ce l
- w r b
_ T o i g N l r cn d E B Ff e B ei o N 8 7 4 t 1 r p 1 R 7 7 7
- O 3 2 3 pt 0 m 0 2 4 4 P O - O mi 0 ru 0l - - -
M N 8 N- um C op D o 0 2 4 O - 5 ps - t - r 3 2 5
_ C 1 1 n 3 c p 1 t
_ 2 D 2 t a 3 am 1 n D D D
_ B R B er B eu C o R R R 2 C 2 Jt 2 R p 2 C C C C T
S
_ E U
Q E
_ 1 5 3 0 4 7 6 3 E
9 6 1 4 8 6 6 6
_ KB 3 0 8 2 0 0 0 0 RM
_ 7 6 7 2 6 6 6 6 OU 8 8 8 8 8 8 8 8
_ WN L L L L L L L L
1 TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER DESCRIPTION M01-2-84-032 Revise the wiring on the control circuitry for' the'2B Diese1' Generator breaker (2433). This will prevent the closure of the 2433 breaker onto the 243' bus if the bus is faulted.
M01-2-84-131 Install a Reactor Vessel Level Instrumentation System per NRC concern in the Generic Letter NO. 84-23.
M01-2-84-0143 Upgrade the primary containment post-accident hydrogen-oxygen monitors, 2PL76J and 2PL77J, to attain a i qualified configuration.
M01-2-86-082 Replace the Rosemount 1152 Flow Transmitter with an l Rosemount 1153 Flow Transmitter on the suction side of the Re-Circulation Pumps to the inlet of the Reactor water cleanup heat exchanger.
M01-2-86-093 Revise the wiring on the control _ circuitry for the "0" Diesel Generator breaker ODG01K. This will prevent the closure of the breaker onto the bus if the bus is faulted.
M01-2-87-058' Removal of the piping,. supports, and equipment installed for the Fine Motion Contol' Rod Drive. -]
M01-2-87-063 Snubber reduction on the RR system, subsystem 2RH01 and 2RRC7A per the snubber reduction program.
M01-2-87-072 Snubber reduction on the LPCS header subsystem per the snubber reduction program.
M01-2-87-079 Snubber reduction on the Feedwater piping subsystem per I the snubber reduction program.
M01-2-87-086 Replace the existing RPS and PCIS reactor water level switches with an analog trip system consisting of Rosemount level transmitters and trip units.
M01-2-87-090 Complete Phase 2 of a bypass line around the main Feedwater low flow regulation valve, 2 FWO S ' .
l l
! M01-2-88-054 Resolve interferences for the Mechanical Stress l Improvement Program (MSIP), permanent modifications to the
. structural steel and to mechanical and electrical component auxiliary steel support are required.
DOCUMENT ID 0036r/0031r
v TABLE 2 (Continued)
COMPLETED SAFETY RELATED MODIFICATIONS' 4
MODIFICATION NUMBIR DESCRIPTION
! s
]
N01-2-88-055 Install insulation on the Main Steam instrument lines associated with Main Steam High-Flow Detection Instrumentation.
M01-2-88-058 Install a counterweight to the A loop.Feedwater Inboard. ,
Isolation Check Vavle (2B21-F010A) disc to correct an !
1mbalance created during past machining.
i l
i l
i i
(
l l
l l
l 1 j l
l l
l I
DOCUMENT ID 0036r/0031r
,i
,a
- C. LICENSEE EVENT REPORTS LER Number Date Description 89-004-00 02/01/89 30 Day-2A RHR Min Flow Bypass # switch >'~
reject limits (SOR) 89-005-00 .02/07/89 30 Day-Closure of 2E12-F008.
1 89-006-00 02/14/89 30 Day-Reactor Low Water Level' confirmed ADS l SOR failure.
1
'l l
l l l N
1 l
l l
l l
i 1 ,
D. DATA TABULATIONS
- 1. Operating Data Report (Attached)
- 2. Average Daily Unit Power Level (Attached)
- 3. Unit Shutdowns and Power Reductions (Attached)
DOCUMENT ID 0036r/0031r
/ # <a a .
..' J. ,
- I
. 1. OPERATING DATA REPORT DOCKET NO. 950-374 UNIT LASALLE TWO 1
, - DATE MARCH io, 1989 I COMPLETED BY J.W.THUNSTEDT TELEPHONE (815)-357-6761
/ t t
OPERATING STATUS
- 1. REPORTING PERIOD: FEBRUARY 1989 GROSS HOURS IN REPORTING PERIOD: 672 2.- CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (We-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net) 1,078 ' i
- 3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Net): (NONE)
- 4. REASONS FOR RESTRICTION (IF ANY): (N/A)
'l REPORTING PERIOD DATA i
. .. ==_. .. .. . .....
{
THIS MONTH YEAR-TO-DATE CUMULATIVE ;
- 5. TIME REACTOR CRITICAL (HOURS) 502.1 502.1 23,980.1
- 6. TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 1,716.9
- 7. TIME GENERATOR ON-LINE (HOURS) 450.5 450.5 23,541.5 j
- 8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0
- 9. THERMAL ENERGY GENERATED (MWHt-Grossi 1,028,904 1,028,904 66,968,512 l
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 332,872 332,872 22,036,210 4
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 319,238 317,211 21,056,461
- 12. REACTOR SERVICE FACTOR (%) 74.7 35.5 62.7
- 13. REACTOR AVAILABILITY FACTOR (%) 74.7 35.5 67.2
- 14. SERVICE FACTOR (%) 67.0 31.8 61.5 i
- 15. AVAILABILITY FACTOR (1) 67.0 31.8 61.5
- 16. CAPACITY FACTOR (USING MDC) (1) 45.9 21.6 53.1
- 17. CAPACITY FACTOR (USING DESIGN MWe) (Z) 44.1 20.8 - 51.1
- 18. FORCED OUTAGE FACTOR (1) 1.5 1.5 16.7
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 4 MONTHS (TYPE, DATE, AND DURATION OF EACH):
(NONE)
- 20. IF SHUIDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
(N/A)
Ja y +
, l
, , ' ' , ._ r - *
. >$0CXETNO. 030-374
= UNIT LASALLE TWO
- 2. AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) .DATE MARCH 10,.1999
, , ' COMPLETED BY J.W. THUNSTEDT'- .i
- TELEPHONE (8151-357-6761 _j
.) .
REPORT PERIOD: FEBRUARY 1989 i
DAY POWER DAY POWER ;;
.. .. ... 1 1 -10 17 687 j
2 -10 18 817 J
{[
3 -10 19, 833 l
~4 -10 20 884
)
5 -11 '21 863 .
l
-6 -22 1,016 , al
~7 -11 23 .1,025 8 -11 24 1,020
.9 25 985 1 '
10- 134 26 1,048 -
11 195 27 -1,051 12 132 28 1,041 13 373 29 l
14 164 30 15 421 31 16 709 i
i l
J l
7* % . .
d e _
S e T p N s E - ..
M r _
M e .
t d
EO v ,_
e1 VC o ,
+
I / . .
t6 TS eg o s7 CN 2 nn .
w n6 EO 0 ii T9 u- RI R bt 4 8h7 RT 2 rs 7 e9 T5 OC L ue :
3l1 l .)
3 CA Tt _
0 a ,J5 .
5S0 1 0 a1Y8 _
.L B( _
h .
OE cDE NMrEN A aTO TNMEH RR E LP NOE KTEPE W W CI TML FORO ONAOE ODOP DUDCT T DGCG 0
ONAN HI EI 4 1 2 TTRC S
ET U N
MUED HHE O STR I
T C 9 U 8 D 9 =
E 1 _
R _ _
E R Y D E R O W A C O U P R N B O C B = .
D E S _
N F A
A _
E _
H R .
S T .
N N -.
W O O M D
T T U R H O -
S P N E O)
T R I S I
N TR 5 0 U
_ RO 1 7 UH 2 D( 2
_ 3 D
D E
L DU ED_
FS r 1
3 8 0 -
8 9 0
- 8 /
5 -
r E 1 2 6 T - 1 3 0
A 0 -
0 D 1 2 L D A I I
T T YNR N LEE E RUB M AQM 1 2 U EEU _ C
~ YSN O D
~ m. - 1 E. UNIQUE REPORTING REQUIREMENTS
- l. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATIONS CONDITION OF EVENT l
(None) : 1
2-273-89 RCIC Condensate Pump Inspect brushes. l l
2-281-89 2E12-F016A Administrative control.
2-293-89 I 1
2E51-F012 Administrative Control. I 2-299-89 2E51-F091CY Clean valve seat.
2-320-89 2E12-F087A Administrative control.
l l
l 2-327-89 (RCIC) Overspeed test. l l 2-334-89 (RHR) Administrative control.
2-372-89 (RCIC) Change 011.
1 j
2-377-89 2DG035 Replace hand wheel.
- 3. Off-Site Dose Calculation Manual (None)
- 4. Major changes to Radioactive Maste Treatment Systems.
(None)
- 5. Indications of Failed Fuel Elements.
(None) l DOCUMENT ID 0036r/0031r
l
.' p C mm:nw;:llth lIdison
,e '
LaSalle County Nuclear StaBon '
\ Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 l
i March 10, 1989' l
)
l Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555 ATTN: Document Control Desk i
Gentlemen:
Enclosed for your information is the monthly performance report covering !
l LaSalle County Nuclear Power Station for February, 1989.
l Very truly yours, O
j G. J. Diederich Station Manager LaSalle County Station GJD/JWT/crh Enclosure ,
1 xc A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle l
Gary Wright, Ill. Dept. of Nuclear Saf ety i I
P. Shemanski, HRR Project Manager l D. P. Galle, CECO l D. L. Farrar, CECO j l INPO Records Center l L. J. Anastasia, AIP Coordinator, Nuclear Services M. A. Ortin, GE Resident H. E. Bliss, Manager of Nuclear Licensing l W. F. Naughton, Nuclear Fuel Services Manager j l
C. F. Dillon, Senior Financial Coordinator, LaSalle l
)
l Dennis Carlson/ Tech Staff Terry Novotney/INPO Coordinator, Tech Staff Central File .l f
i j DOCUMENT ID 0043r/0031r y j i I ;
!