ML20129J449
| ML20129J449 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/31/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20129J447 | List: |
| References | |
| NUDOCS 9611060273 | |
| Download: ML20129J449 (20) | |
Text
. . , . . .. . . - . . _ - - - - . _ . . .- - . -..-- . . - . . - . . . - .. .- . .
i ,
ATTACHMENT B . i PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS ;
V V Xll XII ,
XXI XXI 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 B 3/4 3-4a B 3/4 3-4a l
f l
l i
9611060273 961031 PDR ADOCK 05000373 p PDR
, INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE amjIRENENTS i
SECTION i P,E j 3/4.3 INSTRUMENTATION
! 3/4.3.1 REACTOR PROTECTION ECTEM INSTRUMENTATION. .........
3/47-1 l 3/4.3.2 i
i ISOLATION ACTUATION INSTRUMENTAU 0N.......................... 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION 3/4INSTRLDE 3-23,.
! 3/4.3.4 '
i RECIRCULATION Pt4F TRIP ACTUATION INSTR 18ENTATION i . .
ATWS Recirculation Pump Trip Systas Instrumentation........:. '3/4 3-35 i
End of-Cycle Recirculation Pamp Trip System Instrumentation............................................ 3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM M',TUATION INSTRUMENTATION....................... .................... 3/4 3-45 3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK IN57RUMENTATICM............ 3/4 3-50 3/4.3.7 MONITORING INSTR!#ENTATION
(..
R_adiation Monitoring Instrumentation.....................:... 3/4 3-56 (SeismicMonitoringInstrumentation...........................
Meteorol ogical Monitoring Instrumer.ution. . . . . . . . . . . . . . . . . . . .3/43-6)0 3/4 3-63 Remote Shutdown Moni toring Instnmentation. . . . . . . . . . . . . . . . . . .
3/4 3-66 Accident Monitoring Instrumentation....................... .. 3/4 3-69 Source Range Monitors..................................... . ' . 3/4 3-72 Traversi ng In-core Probe Systes. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3/4 3-73 Deleted......................................................
3/4 3- 74 Fire Detection Instrumentation................... ........... 3/4 3-75 Deleted.......................................... ........... 3/4 3-81 Explosive Gas Monitoring Instrumentation.................... , 3/4 3-82 Loose-Part Detection Systes.................................. 3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.............................................3/4 3-86 k
LA SALLE - UNIT 1 V Amendment No. 85
i
! IN,.p[1 i
BASES
! SECTION EMif 3/4.0 APPLICABILITY................................................ B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.i.i Saur00WN MARGIN................................... B 3/4 i-i l
l 3/4.1.2 REACTIVITY AN0MALIES.............................. B 3/4 1-1 l 3/4.1.3 CONTROL R005...................................... B 3/41-2 i 3/4.1.4 CONTROL R00 PROGRAM CONTR0LS...................... B 3/4 1-3 l 3/4.1.5 STAND 8Y LIQUID CONTROL SYSTEM..................... B 3/4 1-4 l 3/4.1.6 ECONOMIC GENERATION CONTROL SYSTEM................ B 3/4 1-5 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE........ B 3/4 2-1 3/4.2.2 DELETED........................................... B 3/4 2-3 i
3/4.2.3 MINIMUM CRITICAL POWER RATI0...................... B 3/4 2-3 l 3/4.2.4 LINEAR HEAT GENERATION RATE....................... B 3/4 2-6 i - 3/4.3 INSTRUMENTATION
( 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION......... B 3/4 3-1 q g 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION............... B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION................................... B 3/4 3-2 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION. B 3/4 3-3 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION I NST RUMENT AT ION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .8 3/4 3-4 3/4.3.6 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION...... B 3/4 3-4 3/4.3.7 MONITORING INSTRUMENTATION Radi ation Monitoring Instrumentation. . . . . . . . . . . . . . B 3/4 3-4 heismicMonitoringInstrumentation................ B 3k3-4a )
J Y
(W, LA SALLE - UNIT 1 XII Amendment No.113 1
1
. . 7 M
} LIST OF T48LES (Continued) i i
TABLE PAGE Y
3.3.4.1-2 ATWS RECIRCULATION PLSF TRIP SYST M i,
INSTRtMENTATION SETPOINTS . . . . . . . . . . . . . . . . . . . . 3/4 . . . 3-37..
4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION i INSTRUMENTATION SURVEILLANCE REQUIREENTS ......... 3/4 3 ,
3.3.4.2-1 END-0F-CYCLE RECIRCULATION PtMP TR i
INSTRUMENTATION . . . . . ................
. . . . . . . . . . . . . 3/4 .IP3-41 SYSTEM ;
3.3.4.2-2 END-OF-CYCLE RECIRCULATION TRIP SYST M
{
SETPOINTS .~................Pl#F........................ 3/4 3-42 i 3.3.4.2-3 END-DF-CYCLE RECIRCULATION l RESPONSE TIE . . . . .........................
. . . . . . . . PUMP TRIP3/4 SYSTM 3-43 I
- 4. 3. 4. 2.1-1 i END-0F-CYCLE RECIRCULATION P18F TRIP SY 1
1 SURVEI LLANCE REQUIREMENTS ........... . . . . . . 3/4
. . .3-44 . . . . .STM j 3.3.5-1 REACTDR CORE ISOLATION COOLING i
1 INSTRUMENTATION ............... SYSTEM ACTUATION
.................... 3/4 3-46 3.3.5-2 e REACTOR CORE ISOLATION COOLING SYST S
( '
INSTRUMENTATION SETP0INTS ............. ............ ACTUATION 3/4 3-48
} 4.3.5.1-1 '
REACTDR CORE ISOLATION COOLING SYSTEM ACTUATION 3.3.6-1 CONTR0 R0D CK i
i TI ...... 34 -51 i 3.3.6-2 CONTROL'R00 WITHDRAWA j SETP0INTS . . . . ..............................
. . . . . . . L BLOCK INSTRIMENTATION 3/4 3-53 4.3.6-1 CONTROL.R00 WITHDRAWAL BLOCK INSTEMEN 1 SURVEILLANCE REQUIREMENTS ............ .............TATION 3/4 3-54 l 3.3.7.1-1 ..
i RADIATION MONITDRING INSTRUMENTATION .............. 3/4 3-57 4.3.7.1-1 RADIATION MDNITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......................... '3/4 3-59 3.7.2-1 SEISMIC MNITDRIE INSTRUMENTATION ................
! 4.3.7.2-1 SEISMIC MNITORING INSTRIMENTATION 3/43-6k SURVEILLANCE pm3IREMENTS . . . . . . . . . . . . . . . . . . . . . . . . .
3/43-E2)i
! 3.3.7.3-1 i, METEORDLDGICAL WNITDRING INSTRIMENTATION 3/4 3-64.........
)
i b
i LA SALLE - UNIT 1 XXI l- Amendment No. 18 4
4 .
I ENTATION j SEISMIC MONITORING INSTRUMENTATION *
- 'N LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall I be OPERABLE."
1 j
- APPLICABILITY
- At all times. '
f I
i ACTION:
j . .
- a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepara and submit a Special Report to the Commission pursuant to Specification.6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the .
j instrument (s) to OPERABLE status, l
- b. The provisions of Specification 3.0.3 are not applicable. .
SURVEILLANCE REOUTREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be j
demonstrated OPERABLE by the perfomance of the CHANNEL CHECK, CHANNEL
- FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies snown
] -
(- in Table 4.3.7.2-1.. ..
1 4.3.7.2.2 Each of the above required, seismic monitoring instruments actuated .
during a seismic event greater than or equal to 0.02g shall be restored to i
OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within
- 5 days following the seismic event. Data shall be retrieved from actuated !
! instruments and/ analyzed to detemine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the cosaission pursuant to Specification 6.6.C within 10 days describing the magnitude, fre-
- quency spectrum'and resultant effect upon unit features important to safety.
4 i
V
- 6 MTEuTtou Ally LCfT D'A'4k- ~
l 1
a 3c.,.3/4 s- u a s/+ a t 0clet d F f j
i -
stat ctnicLE D cN PAbt 4
i _
( -
.The Seismic Honitoring Instrumentation System is shared between La Salle 4
' Unit 1 and La Salle Unit 2.
"The normal or emergency power source may be inoperable in OPERATIONAL j C
%_0NDITION 4 or 5 or when defueTed.
l ,: w ie "NtT 1 3 n 3-60 bed fue is 5kJ4M t-as-n-+ nn e
J .
.. v-TABLE 3.3.7.P-1 C MONITORING INSTRUMENTATION
_ i
- MINIMUM DEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE {
OPERABLE )
- 1. Triaxial Time-History Accelerographs
- a. Containment Foundation E1. E738-4*
113,10s:1 tbmasic 1
- 4. range. 0-32 k -
Containment structurs !,1 3,IP:1 $namic E1. 820'-E' 1
- c. Free Field range, 0 32 h 2,13,1r:1 & namic 1
- d. Aun. Elec. Equip. Roos range. 0-32 Hz Ig,IP:1 & namic 1
-l range 0-32 h 1
- 2. Triaxial Peak Accelerographs
- a. SGT5 1 Ig, 20:1 @namic . 1
~ '
- b. range, 0-20Hz A RHR Line in Reactor ! Ig, 20:1 $namic ,
guilding Rotunda 1 '
- c. range. 0-20Hz HPCS Diesel Generator ! Ig, 20:1 @namic
(- d.
Control Panel .
range, 0-20Hz 1
Main Control Soard 31g, 20:1 &namic *1
, range 0-20Hz 3.
Triaxial Seismic Switches ,
- a. Containment Foundation El. ET3'-4" 0.005 to 0.15 g 1
- b. adjustable Internal Trigger (b) adjustable 1(a)
- 4. Triaxial Response-spectrum Recorders
- a. Terra Tech. Digital Cassette with playback feature - 1.0g to - 0.05 g 1
+ 0.05 g to 1.0 g
(*)With reactor control roes annunciation.
I Adjustable setpoint.
LA SALLE - UNIT 1 1/4 3-El .
T r TABLE 4.3.7.2-1 SEISNIC MONITORING I"NSTRUNENTATION SURVEILLANCE REQUIREMENTS CHAMtEL CHANNEL RMCTIONAL CHANNEL INSTRUNENTS AND SENSOR LOCATIONS -
CHECK TEST CALIBRATION
- 1. Triaxial Time-History Accelerographs .
- a. Containment Foundation M SA R
- b. Containment Structurs M SA R
- c. Free Field N SA R
- d. Aux. Elec.. Equip. Room M SA R
- 2. Triaxial Peak Accelerographs
~~'
- a. SGTS NA MA R -
- b. RHR Line in Reactnr Building NA NA R Rotunda
- c. HPCS Diesel Generator Control NA NA R Panel f
- d. Main Control Board NA' NA R -
- 3. Triaxial Seismic Switches S
(' a. Containment Foundation I M*I f' '
? 5A ., R l., Internal Trigger
- b. N --
' 5A ~ R
- 4. Triaxial Response-Spectrum Recorders '
- a. Terra Tech. D'igital Cassette M' SA R with playback feature
. l
~' l
(*)Except seisaic Yrf'gger. '
)
l t'
- 3 .
i LA SALLE - UNIT 1 3/4 3-E2
~
\
w -
e 6. me esa e e enmee e e .
o e - - - - - - - - - - - - - - - - - - --
, ins?PUMENTATIDH BAFEF a ,
ETEMTc MONTTORTNC TMETRtFrMT1?TO MbNh The OPERABILITY of the seismic monitoring instrumentation ensures tha sufficient capability is available to promptly determine the magnitude of a s
seismic event and evaluate the response of those features important to safety. t This capability is required to permit comparison of the measured response to I that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12
- Instrumentation /l i
for Earthquakes *. April 1974. > ./ i h 3.7.3 wrtromot Ocf ra f. MOwTTontwe TwfTatfwrweavTom a that The OPERABILITY of the meteorological monitoring instrumentation ensures sufficient meteorological dsta is available for estimating potential radiation doses to the public as a result of routine or accidental release of {
radioactive materials to the atmosphere. This capability is required to !
evaluate the need for initiating protective measures to protect the health and safety of the public.
)
This instrumentation is consistent with the recommenda-tions 1972. of Regulatory Guide 1.23 'onsite Meteorological Programs,* February, 3/a.3.7.d aFMotr NMtfTDOWN MONTTORTNC TWRTRtT47a ikTTON that The OPERABILITY of the remote shutdown monitoring instrumentation ensures sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
(
1
~
I LA SALLE - UNIT 1 5 3/4 3-4a Amendment No.104
~.. . ;
_. _ m_ . ewr>E
. _ - -. . . . d :.:.-
i 5 W3 .;. %..S $ $:W W - W W 5.*.d.:..
- l'
. .-.w.=-- .
..w.w.- s-
.I E LImme c0em0Ns roa oPEtan0N Am simIn =- -->In4_.s.
E.UIE E
3/4.3 INSTRUMENTATION
.3/4. 3.1 -
REACTOR PROTECTION SY37EN INSTRtserTATION. .. . 3/4 .
. . ..3-1 3/4.3.2 ISOLATION ACTUATION INSTMsGfrATION.......................... 3/4 3-9 3/4.3.3 EERGENCY CORE COOLING SYSTEM ACTu4 TION 2N57R14WfTATION 3/4 3-23..
3/4.3.4 RECIRCULATION PUW TRIP.ACTu4 ..... ..
TION INSTRiaWITATIINf - -
ATWS Recirculation Puup Trip Systa's Instrumentation.......... 3/4 3-35 End-of-Cycle Recirculation Pump Trip Systes Instrumentation............................................ 3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION C00LIldi SYSTEM ACTUATION INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 . . .3-45 3/4.3.5 CONTROL, .300 WITHDitAW4L BLOCK INSTRiseffATI0N............... ..
3/4 3-50 3/4.3.7
( MONITORING INSTR 18Ef7ATION
. ~
Radi at i on Moni tori ng Instramentati on. . . . . . . . . . .'. . .
. .. . . . ' . . '3/4. . 3-57 Seismic Monitoring Instrumentation........................... 3/4 3-50 Meteorological Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . .
3/4 3-53 Remota shutdown Monitoring Instrumentation. . . . . . . . . . . . . . . . . . .
3/4 3-55 Accident Monitoring Instrumentation.......................... 3/4 3-59 Source Range Monitors........................................ 3/4 3-72 Travers i ng In-core Probe 5ys taa. . . . . . . . . . . . . . . . . . . . . . . 3/4 . . . 3-73 Deleted.....................................................- 3/4 3-74 Fi re Detection Instrumentati on. . . . . . . . . . . . . . . 3/4 . . .3-75............
Deleted...................................................... 3/4 3 31
, Empl exi ve Gas Moni tori ng Instrumentation. . . . . . . . . . . . . . . . . . . . .
3/4 3-32 Loose-Part Detection 5ystas.................................. 3/4 3-85
{.- '. 3/4. 3. 8 FEEDWATER/ MAIN TINtBINE TRIP SYSTEM ACTUATION INSTRUNENTATION.............................................3/4 3-36 LA SALLE - UNIT 2 V Amen h nt ho. 69 wh _
- . \
l 18D11 '
I i
BASES
- l
{ SECT 10N PAGE
! 3/4.0 APPLICABILITY................................................. B 3/4 0-1 1
i 3/4.1 REACTIVITY CONTROL SYSTEMS 1
)
3/4.1.1 SHUTDOWN MARGIN.................................... B 3/4 1-1 ,
l l 3/4.1.2 REACTIVITY AN0NALIES............................... B 3/4 1-1 j 3/4.1.3 CONT RGi. R005 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 1 -2 i
j 3/4.1.4 CONTROL R00 PROGRAM CONTR0LS....................... B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM...................... B 3/4 1-4 3/4.1.6 ECONOMIC GENERATION CONTROL SYSTEM. . . . . . . . . . . . . . . . . B 3/4 1-5 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE............ B 3/4 2-1 3/4.2.2 DELETED............................................... B 3/4 2-3 3/4.2.3 MINIMUM CRITICAL POWER RAT!0.......................... B 3/4 2-3
( 3/4.2.4 LINEAR HEAT GENERATION RATE........................... B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRWENTATION........ . . B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................ B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................... B 3/4 3-2 3/4.3.4 RECIRCULATION PUMP TRIP ACTu4 TION INSTRUMENTATION.. B 3/4 3-3 3/,4.3.5 REACTOR CORE ISOLATION C0OLING SYSTEM ACTUATION INSTRUMENTATION................................... 8 3/4 3-4 3/4.3.6 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION....... B 3/4 3-4 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............... B 3/4 3-4 feismicMonitoringInstrumentation.................B3/43-4a l
- k. LA SALLE - UNIT 2 XII Amendment No. 98
- - - - - - ____--a n_,..-;..,..
-n m M D F_ " G- - - -"-uM - *
- Nat.
, , w- _
. __- . = = . *
- 4_ _ . _ .h *Y $*b.
~~,'
~ ~~*
- . . 4.a. ... ,
.- ~~
LIST OF TABLES (Continued) TABLE
.P.AE 3.3.4.1-2 ATWS MCIRCULATION Pur TRIP SYST M JNSTRMNTATION SETPOINTS . . .. .. . . . . .. . . . . . . ..3/4 . . .3-37 4.3.4.1-1 ATWS MCIRCULATIM PL8F TRIP ACTUATION INSTRuMENTAUON SURVEILLANCE REQUIRMENTS .........
3/4 3-38 3.3.4.2-1 ' Es-OF-CYCu RECIRCULATION PUNP TRIP SYSTM INSTR M NTATION ................................... 3/4 3-41 3.3.4.2-2 END-0F-CYCLE RECIRCULATION SETPCINTS . . . . . . . ..... . . ...................
. . . . . . . .M8F TRIP SYSTR 3/4 3-42 3.3.4.2-3 EM-0F-CYCLE McIRCULATION RESPONSE TM . . . . .........................
. . . . . . . . M4F. TRIP SYSTM 3/4 3-43 '
4.3.4.2.1-1 EM-OF-CYCLE RECIRCULATION PL#F TRIP . SURVEILLANCE REQUIREMENTS . . . . . . . .3/4
.............. . .3-44
. SYSTM 3.3.5-1 MACTOR COE ISOLATION COOLIE INSTRUMENTATION ............... SYSTEM ACTU4
.................... 3/4 3-46 TIN 3.3.5-2 REACTOR CORE ISOLATION C00 LIE SYSTM -
.- INSTRUMENTATION SETPOINTS ............ ACTUATION
............. 3/4 3-48
(' 4.3.s.1-1 REACTm COE IS0aHON C0auW SYSTM ACTLEUM - INSTRuMENTAD ON S W VEILMNCE EQUIREMENTS ' 3/4 3-49 ......... 3.3.6-1 CONTRDL A00 WITERAWAL BLOCK INSTRL#tENTATION 3/4 3-51 ...... 3.3.6-2 CONTROL 200 WIT E RAWA ' SETPOINTS . . . . .............................
. . . . . . . .L BLOCK INSTRL#tENTATION 3/4 3-53 4.3.6-1 CONTROL R00 WIT E RAWAL SLDCK INSTRL4t SURVEILLANCE REQUIRDIENTS ...........ENTATION
.............. 3/4 3-55 3.3.7.1-1 RADIATION MTORING INSTRUMENTATION .3/4 . .3-58
- 4. 3. 7.1-1 RADIATION NDNITORING INSTRUMEKTATION SURVEILLANCE REQUIREMENTS ......................... 3/4 3-59
/s.3.7.s1 SEISMIC m TORING INSTRUMENTATION ................ 3/4 3-s1
' 4.3.7.2-1 SEISMIC M NITORING INSTRUNENTATION SURVEILLANCE am'IREENTS . . . . . . . . . . .3/4 . . 3-62 3.3.7.3-1 METE 0MLOGICAL MDNITORI E INSTRUMENTAU0N 3/4 3-64 .........
4.3.7.3-1 METEOROLOGICAL MTDRING INSTRMNTA . .. SURVEILIANCE REQUIREMENTS . . . . . . . .3/4 . .3-65
. . TION .... . .
N: LA SALLE - UNIT 2 XXI
~
NSTRUMENTATION
- SEISMIC MONITORING INSTRUMENTATION
- i LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.**
APPLICABILITY: At all times. E' .
- a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,
- b. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1. ( 4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.02g shall be restored to OPERABLE status within 24 hours and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved from actuated I l instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.6.C within 10 days describing the magnitude, fre-quency spectrum and resultant effect upon unit features important to safety. w T INTE4TioMALW Lf.FT 6LAwK ikge> 3/4 5-ci d 5/4 342. Deleied i U tmcd.T ce:etceCD on PA4E. ( *The Seismic Monitoring Instrumentation System is shared between La Salle Unit I and La Salle Unit 2.
**The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.
LA SALLE - UNIT 2 3/4 3-60fmt np n 3/4 M'd Amendment No. 78
* . . mmhmthq.pp.y.wwwv. %m 3..,. . . , -. . - . ... . w.
.b E~ N 'f.[
;.. 2 ~~.. - - ~s.mt -,sr.:wr _ - - - -
_u
.-=.--
,e m .. m. ..,,y.r r . .. .
-\.:.w-:
' " J *
.~
- TABLE hLL2-1
'stisqc IWIITORIM DesTaserTATItpl , -
IEDEDul DesTaperfs AW 381506 lac 4TISIIP masuiseer zusTaserfs - RUIRE
. 0PDABLE -
2 THesial Tiss-tHstory Accelersprophs ,
- a. Centaineest Foundstfee E1. E73'-48 + 3g, 308:1 gynesis 1
- k. rents.,3-31les. .,,
Centainoast stressure ' 13, us:1 We E. 330'=08. 1 rangs, FB ler. c. Pres Ptold .-
- 13' 3gs 1 eneste 1
& ~ A us. El es. Egstp. Bas e resse, FM k. , .
$33, 3gssg g 1 am range < ,
L THesial Peak Acealeregraphs
- a. 5 75
't3g, 3:f*4msnts '
( 2.
, *c .' .
romen, e-. ate
- k. A K L1ne fr Beester Asfidfag Betuada
. ~ Ig, 3:1 temste .. I ~
- c. rangs, 4=Ints W C5 Die +
trei ,sel s.siGenerster ' 3 23, 3:1 e.n.es.ts , t. i 1 Itsis Centrol Board + 13, 3:1 Wassfc 1 range, esser
- 3. . ;
Triesial Setaufe switches '
- a. .
Centalement Foundstfes
' D. 813*=4*
8.se to 8.35 g i h.. entesteh1e Interest $,. germ edustehle 1("I * * *
- 4.
- Trierfal " ,' i ~; h Recorders
.. e.: .
a Terra TesE Digital Cassette with playback feature - 1.0g te - 3.05 g 1
+ 0.05 g to LS g
\
I (*htith reacter sentrol ennuncietfen.
. (b)4 W h W & .
"~~~~-~~'~
~~~-~~~~~~'
- s. ,
*All seismic sensors and listruments are located is La Salle Unit 1 LA SALLE - LMIT 2 ~
1 3/4 Ps2. l l
...M. - _ _ _ w . m. . . >. . . . . . .s . _ r,_, __...w
._ .._ D r i i 1:.'. C'7V%
. -. .w.=2
- m. w.a ::,..e..
w MuJi r--.. .'?%.
- w. . :-...--M.4-u.- : . - - - . .-a..e.~&#W'.?iT***'_ mv .'=. -w -
_ , ,.y.
,, 4 .
..gran?.: ..
. -3 - .
TAELE 4.S2.2=1 w- . . 31sGC IEstITORINE DISTIR8SffATION SURVIILufG RExlIREPUf5
~
CNMBE, - gNMeiL *
'N CMMWEL
* - u. , a .n ., - : ' . ..
.. . ~.t r v -
M TEET M- ,
- 2. Trfasfal 71as fHetery Amoeleregraphs
- a. Cantalamont Femmestian N h.
SA - R -
' Castafamest Structure N ... S 5 .-
- t. Free Field R S 8
& Aus. Eles. Equip. Ross ~ . !
R, SA E ,! . L Triasfai Peak Ascalarsgraphs I a LA.
. .' h. SE MT5 Li 'se is SeestIsr Buf1dfas R.A.
R.A. R
. astunda - '
A.A. ' t- '
- c. Irts 9 fame 1 Esmerstar Castrei panet R.A.
- E.A. E A finia Castret teart
- 5.A.
E.A. E -
- 3. .T.riasfal lefamic Arttshus -
L'- .
- a. Chatafammet Foundstfasr .
4 .
'Sn .
- h. Interest TM m er- ., t
_ N 5 E 4. s-Trfasial Response-Spectrus tesorders a. Terra Tech. Olgtta! Cassetto 'N
- SA wfter playtosk. feature R
. Q.. i,.e ,
. . k, . -v. ;.et
. N.qs.M. .
... d..: .. . .e.+.T .
~
' .=:.,.;' &.m.*,+.:; ..w -Q.,Y2. * ,
e
~ '
I"3 I Escept selaufs trfger. ~
"All seismic sensors and fastr$nnts are located la La Salle ustt 1.
. * * -- m e- -- e -
_ se C l i LA SALLI - UNIT 2 3/4 3-41 e
IN2TRUMENTATIog aien 3/4.3.7.2.
- 2. u .e (arrme wonrrosm. .
The OPERASILITY of the seismic monitoring instrumentation ensures
'---"mmerQ sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the recponse of those features important to safety. i This capability that used is design in the requiredbasis to permit comparison for the unit. Thisof the measured response to l
instrumentation is < consistent with the Earthquakes *, recommendations April 1974. of Regulatory Guide 1.12 " Instrumentation 3/4.1.7.1 METEORotocTeant. MGai 1 Tue T aintrei-iatfoM that The OPERABILITY of the meteorological monitoring instrumentation ensures sufficient meteorological data is available for estimating potential radioactivedoses radiation to the materials public to the as a result of routine or accidental release of atmosphere. This capability is required to evaluate the need safety of the public. for initiating protective measures to protect the health and This instrumentation is consistent with the recommenda-tions of Regulatory Guide 1.23 "Onsite Meteorological Programs
- Pehruary 1972. ,
1/ 4 .1. *F . d RPMoTr inbi n au-11u e Tar! Taa1=b4EaintfoM The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit (
~
room. from locations outside of the control lost and is consistent with General Design criteria 19 of 10 cra 50.Thi l LA SALLE - UNIT 2 3 3/4 3-4a Amendment No. 90
~
e l ATTACHMENT C l SIGNIFICANT HAZARDS CONSIDERATION This is a proposed change to Technical Specification 3/4.3.7.2, " Seismic Monitoring j instrumentation", Table 3.3.7.2-1, " Seismic Monitoring Instrumentation", Table 4.3.7.2- l 1, " Seismic Monitoring Instrumentation Surveillance Requirements", and Bases Section j 3/4 3.7.2," Seismic Monitoring Instrumentation". Comed proposes to relocate these 1 Technical Specifications requirements to licensee-controlled documents as discussed ! in Generic Letter 95-10, Relocation of Selected Technical Specifications Requirements ; Related to Instrumentation. The requirements for seismic monitoring instrumentation, t including a list of the components, will be included in the UFSAR and will be added to l the Administrative Technical Requirements. This change is required as a result of a Modification which replaces existing seismic ) monitoring instrumentation in Panel OPA11J with new instrumentation which are not l "like-for-like" replacements. These instrument replacements will directly impact the contents of Tables 3.3.7.2-1 and 4.3.7.2-1, which contain descriptions of the l instruments. Comed has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on , the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:
The function of the seismic monitoring instrumentation is to monitor seismic activity above the Operating-Basis Earthquake (OBE) threshold, and to record observed seismic data for comparison to design basis response spectra. The seismic monitoring instrumentation does not provide any function to mitigate an accident or the consequences of an accident. The replacement seismic monitoring instrumentation will remain in place. The proposed Amendment is not a result of any changes to system function, alarm setpoints, or main control room annunciators. Rather, the Technical Specification requirements (as revised for the replacement instrumentation) are being relocated to licensee-contro!'ed documents in accordance with NRC Generic Letter 95-10. l The proposed change relocates requirements and surveillances for structures, systems, components or variables that do not meet the criteria for inclusion in Technical Specifications as identified in the Application of Selection Criteria to C-1
)
i i ATTACHMENT C
- SIGNIFICANT HAZARDS CONSIDERATION ;
i 1 ! i ,_ the LaSalle Technical Specifications. The affected structures, systems, j
- components or variables are not assumed to be initiators of analyzed events ;
- and are not assumed to mitigate accident or transient events. The !
j requirements and surveillances for these affected structures, systems, ( j components or variables will be relocated from the Technical Specifications to j an appropriate administratively controlled document which will be maintained ;
- pursuant to 10 CFR 50.59. . In addition, the affected structures, systems, " i y components or variables are addressed in existing surveillance procedures
- which are also controlled by 10 CFR 50.59 and subject to the change control l provisions imposed by plant administrative procedures, which endorse :
- applicable regulations and standards. Therefore, this change does not involve
- a significant increase in the probability or consequences of an accident l previously evaluated.
1 L 2) Create the possibility of a new or different kind of accident from any accident - j previously evaluated because: ! ) 4 The seismic monitoring instrumentation does not provide any function to r
- mitigate an accident or the consequences of an accident. The replacement j seismic monitoring instrumentation will remain in place and will provide the ,
same basic function as the existing instrumentation. The replacement j i instrumentation will provide enhanced system reliability and will not result in any changes to system function, alarm setpoints, or main control room ; annunciators. The Technical Specification requirements (as revised for the ! replacement instrumentation) are being relocated to licensee-controlled 4- ] documents in accordance with NRC Generic Letter 95-10. 1 i l
- The proposed change does not involve any change in the methods governing 1- normal plant operation. The proposed change will not impose or eliminate any l requirements and adequate control of existing requirements will be maintained.
Thus, this change does not create the possibility of a new or different kind of
- accident from any accident previously evaluated.
i s l l } C-2 i 4 i t ~
, - - - ._ . ...~. - ,, , - - - ,
1.
?
c i 1 ATTACHMENT C j SIGNIFICANT HAZARDS CONSIDERATION , 1 1
- 3) Involve a significant reduction in the margin of safety because:
l !
! The replacement seismic monitoring instrumentation will have no impact on j margin of safety. The intended function of the seismic monitoring instrumentation, i.e. to record observed seismic data for analysis to determine ;
i the impact on plant components, will be made more reliable by this
'_ modification. The Technical Specification requirements (as revised for the 1 replacement instrumentation) are being relocated to licensee-controlled documents in accordance with NRC Generic Letter 95-10.
l I 4 The proposed change will not reduce a margin of safety because it has no
- impact on any safety analysis assumptions. In addition, the relocated l requirements and surveillances for the affected structure, system, component or variable continue to meet the same requirements as the existing Technical {
i l Specifications. However, the LCO requirement specified in Section 3.3.7.2.a (to j prepare and submit a Special Report to the NRC within 10 days of the seismic ] monitoring instrumentation being inoperable for more than 30 days) will not be ; i included in the ATR since the Technical Specification Special Report i requirements are only applicable to the LCOs. Since any future changes to 7 these requirements or the surveillance procedures will be evaluated per the ! i requirements of 10 CFR 50.59, no reduction in a margin of safety will be i j permitted. ; 4 f , The existing requirement for NRC review and approval of revisions, in ! accordance with 10 CFR 50.92, to these details proposed for relocation does ! not have a specific margin of safety upon which to evaluate. However, since ) } the proposed change is consistent with the BWR Standard Technical ! l Specification, NUREG-1434, Rev.1 approved by the NRC Staff, revising the ! 4 Technical Specifications to reflect the approved level of detail ensures no : l significant reduction in the margin of safety. i i ' Guidance has been provided in " Final Procedures and Standards on No Significant i Hazards Considerations," Final Rule, 51 FR 7744, for the application of standards to 1 license change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are and are i not considered likely to involve significant hazards considerations. These proposed { amendments most closely fit the example of a change which may either result in some increase to the probability or consequences of a previously analyzed accident or may i l C-3 7 1 4 . l
\
l ATTACHMENT C l SIGNIFICANT HAZARDS CONSIDERATION l reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the ; Standard Review Plan. ' This proposed amendment does not involve a significant relaxation of the criteria used , to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant relaxation of the bases for the limiting conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration. ' l l l 1 l l ! i l 4 C-4 I
~
ATTACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW
~
Comed has evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR Part 51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR Part 51.22(c)(9). This conclusion has been determined because the changes requested do not pose significant hazards considerations or do not involve a significant increase in the amounts, and no significant changes in the types of sny effluents that may be released off-site. Additionally, this request does not invclve a significant increase in individual or cumulative occupational radiation exposure. i t 1 I l _ _}}