ML20107F064
| ML20107F064 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/16/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20107F058 | List: |
| References | |
| NUDOCS 9604220208 | |
| Download: ML20107F064 (46) | |
Text
A'ITACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS NPF-11 NPF-18 3/4 3-6 3/4 3-6 Insert A Insert A 3/4 3-18 3/4 3-18 l i
3/4 3-19 3/4 3-19 l
! Insert B Insert B l 3/4 3-31 3/4 3-31 Insert C Insert C i B 3/4 3-1 B3/43-1
- Insert D Insert D l B 3/4 3-2 B 3/4 3-2 1 Insert E Insert E
- Insert F Insert F i
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9604220208 960416 PDR ADOCK 05000373 P PDR
L TA8tE 3.3.1-2 i 5
g REACTOR PROTECTION SYSTEM RESPONSE TIMES l-m e RESPONSE TIME i g FUNCTIONAL UNIT (Seconds) !
- 1. ;
" Neutron Flux - High*
- a. NA
- b. Inoperative NA l
. . j
- 2. Average Power Range Monitor *
- a. Neutron Flux - Hfgh, Setdown ~
NA ..
- b. Flow Blased Simulated Thermal Power-Upscale < 0.09
- c. Ffxed Neutren Flux - High i 0.09
- d. Inoperative liA w 3. Reactor Vessel Steam Dome Pressure - High < 0.5 1 4. Reactor Vessel Water Level - Low, tevel 3 71.0 O w 5. Main Steen Line Isciation Valve - Closure 7 0.06 J. 6. Main Steam Line Radiation - High liA
- 7. Primary Containment Pressure - High NA
- 8. Scram Discharge Volume Water tevel - High NA
- 9. Turbine Stop Valve - Closure -< 0.06
- 10. Turbine Control Valve Fast Closure, Trip 011 Pressure - Low < 0.08#
- 11. Reactor Mode Switch Shutdown Position RA *
- 12. Manual Scram NA l
- 13. Control Rod Drive
- a. Charging Water Header Pressure - Low NA Delay Timer
- b. NA
{ " Neutron detectors are exempt from response time testing. Response time shall be measured
~
fron the detector output or from the input of the first electronic component in the channel. '
s **Not including simulated thermal power ting constant.
- Measured from start of turbine control valve fast closure. MS84'78 '
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_ . _ _ _ _ _ - _______..._______m._ _____________-__- _____-__ ___ _ _ _ _ __ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - - _ _ _ _ _
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT A l (Proposed footnote for Table 3.3.1-2)
Sensor is eliminated from response time testing for the RPS circuits. I Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.
i B-2
I l TABLE 3.3.2-3
- ISOLATION SYSTEM INSTRUMENTATION. RESPONSE TIME l TRIP FUNCTION RESPONSE TIME (Seconds)#
A. AUTOMATIC INITIATION i
- 1. PRIMARY CONTAINMENT ISOLATION ,
l 1) Low, Level 3 N/A' l 2) Low Low, Level 2 N/A l 3) Low Low Low, Level 1 1.0*N l 1
l b. Drywell Pressure - High N/A
> c. Main Steam Line i 1) Radiation - High M 1.0*M i 2) Pressure - Low s 2.0* #
l 3) Flow - High 05*M !
l d. Main Steam Line Tunnel Temperature - High i j e. Condenser Vacuum - Low N/A
- f. Main Steam Line Tunnel ATemperature - High N/A
- i. '
j 2. SECONDARY CONTAIMiENT ISOLATION N/A i a. Reactor Building Vent Exhaust Plenum l l Radiation - High j b. Drywell Pressure - High -
- c. Reactor Vessel Water Level - Low, Level 2
- d. Fuel Pool Vent Exhaust Radiation - High
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION N/A .
- a. AFlow - High
! b. Heat Exchanger Area Temperature - High l c. Heat Exchanger Area Ventilation AT-High
- d. SLCS Initiation
- e. Reactor Vessel Water Level - Low Low, Level 2
- 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION N/A-l a. RCIC Steam Line Flow - High
, b. RCIC Steam Supply Pressure - Low i c. RCIC Turbine Exhaust Diaphragm Pressure - High
! d. RCIC Equipment Room Temperature - High
- e. RCIC Steam Line Tunnel Temperature - High '
! f. RCIC Steam Line Tunnel ATemperature - High j g. Drywell Pressure - High a h. RCIC Equipment Room ATemperature - High I
! 5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION N/A i
i a. RHR Equipment Area ATemperature - High
! b. RHR Area Cooler Temperature - High j c. RHR Heat Exchanger Steam Supply Flow High i
)
i j LA SALLE - UNIT 1 3/4 3-18 AMENDMENT NO. 98 l .
TABLE 3.3.2-3 (Continued)
JSOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Secondsf
- 6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION N/A
- a. Reactor Vessel Water Level - Low, Level 3
- b. Reactor Vessel (RHR Cut-In Permissive
- c. RHR Pump Suction Flow -) HighPressure - High
- d. RHR Area Cooler Temperature High
- e. RHR Equipment Area AT High B. MANUAL INITIATION N/A
- 1. Inboard Valves
- 2. Outboard Valves
- 3. Inboard Valves
- 4. Outboard Valves l
- 5. Inboard Valves 't
- 6. Outboard Valves ;
- 7. Outboard Valve TABLE NOTATIONS l
- Isolation system instrumentation response time for MSIVs only. No diesel l generator delays assumed.
t Radiation detectors are exempt from response time testing. Response time shall be measured from detector output or the input of the first electronic component in the channel.
Isolation system instrumentation response time specified for the Trip Function actuating the MSIVs shall be added to MSIV isolation time to l
obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
- meRTB l
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N/A Not Applicable, i
l LA SALLE - UNIT 1 3/4 3-19 Amendment N,0. 102
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l ATTACHMENT B
, PROPOSED AMENDMENTS TO THE j LICENSE / TECHNICAL SPECIFICATIONS INSERT B (Proposed footnote for Table 3.3.2-3) l ## " Sensor is eliminated from response time testing for the MSIV actuation l logic circuits. Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are I required." '
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TABLE 3.3.3-3 l l
EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES l ((.Gji RESPONSE TIME (Seconds)
- 1. LOW PRESSURE CORE SPRAY SYSTEM s60*M l
- 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Pumps A, B, and C) s60*)h
- 4. HIGH PRESSURE CORE SPRAY SYSTEM g 41 k
- 5. LOSS OF POWER NA 1
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- Injection valves shall be fully OPEN within 40 seconds after receipt of the reactor vessel pressure and ECCS Injection Line Pressure Interlock signal.
concurrently with power source availability and receipt of an accident initiation signal.
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i LA SALLE - UNIT 1 3/4 3-31 Amendment No. 96
ATTACHMENT B
- PROPOSED AMENDMENTS TO THE l LICENSEffECHNICAL SPECIFICATIONS l INEERT C l
(Proposed footnote for Table 3.3.3-3) l l
- "ECCS actuation instrumentation is eliminated from response time testing."
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3/4.3 INSTRUMENTATION BASES l
l l 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION i
j The reactor protection system automatically initiates a re2ctor scram to:
l a. Preserve the integrity of the fuel cladding.
I i b. Preserve the integrity of the reactor coolant system.
l c. Minimize the energy which must be adsorbed following a loss-of-I coolant accident, and I
! d. Prevent inadvertent criticality.
l This specification provides the limiting conditions for operation
! necessary to preserve the ability of the system to perform its intended
! function even during periods when instrument channels may be out of service j because of maintenance. When necessary, one channel may be made inoperable
! for brief intervals to conduct required surveillance.
i The reactor protection system is made up of two independent trip systems.
l There are usually four channels.to monitor each parameter with two channels in each trip system. The outputs of the channels in a trip system are con 31ned in a logic so that either channel will trip that trip system. The tripping of
! both trip systems will produce a reactor scram. The system meets the intent
! of IEEE-279, 1971, for nuclear power plant protection systems. Specified I surveillance intervals for MSIV-Closure, TSV-Closure, TCV-Closure, and the l Manual Scram have been determined in accordance with NEDC-30851P-A, " Technical i Specification Improvement Analyses for BWR Reactor Protection System", March 1 1988. The bases for the trip settings of the RPS are discussed in the bases l for Specification 2.2.1.
~
! The measurement of response time at the specified frequencies provides l assurance that the protective functions associated with each' channel are com-
! plated within the time limit assimed in the accident analysis. No credit was
! taken for those channels with response times indicated as not applicable.
I Response time may be demonstrated by any series of sequential, overlapping or j total channel test measurement, provided such tests demonstrate the total
! channel response time as defined. Sensor response time verification may be
! demonstrated by either (1) inplace, onsite or offsite test measurements, or i (2) utilizing replacement sensors with certified response times.
l 5tM TD i
l LA SALLE - UNIT 1 B 3/4 3-1 AMENDMENT NO. 95 l
l
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS INSERT D The measurement of response time at the specified frequencies provides assurance that the protective functions associated with each channel are com-pleted within the time limit assumed in the accident analysis. The RPS RESPONSE TIME acceptance criteria are included in plant Surveillance procedures. Only those functions with times assumed in the accident analysis are required to be response time tested.
As stated in Note
- of Table 3.3.1-2, Neutron detectors are exempt from response time testing. In addition, for Functional Units 3 and 4, per Note #,the associated sensors are not required to be response time tested. For these Functional Units, response time testing for the remaining channel components, including any analog trip units, is required. This allowance is supported by NEDO-32291-A, " System Analyses for the Elimination of Selected Response Time Testing Requirements," October 1995.
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
B-5 t
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- INSTRUMENTAIl0N I
BASES i
3/4.3.2 ISOLATION ACTUATION INSTRtMENTATION l This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and response times for isolation of the reactor systems. When j
! necessary, one channel may be inoperable for brief intervals to conduct l l required surveillance. Both channels of each trip system for the main steam l
i tunnel ambient temperature and ventilation system differential temperature may i
be p1 aced in an inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required reactor l
!. building ventilation system maintenance and testing and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the 1 l required secondary containment Leak Rate test without placing the trip system 4
in the tripped condition. This will allow for maintaining the reliability of ;
! the ventilation system and secondary containment. Some of the trip settings i i may have tolerances explicitly stated where both the high and low values are j critical and may have a substantial effect on safety. The setpoints of other i instrumentation, where only the high or low and of the setting have a direct i bearing on safety, :re established at a level away from the normal operating range to prevent inadvertent actuation of the systems involved. l l Except for the MSIVs, the safe':y analysis daes not address individual i sensor response times or the respcase times of the lo ic systems to which the
! sensors are connected. For A.C. operated valves, it s assumed that the A.C. I i
power supply is lost and is restored by startup of the emergency diesel
! generators. In this event, a time of 13 seconds is assumed before the valve j
starts to move. The safety analysis considers an allowable inventory loss l4 l which in turn determines the valve speed in conjunction with the 13 second
- delay. y i
k 3/4,3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION j
The emergency core cooling system actuation instrumentation is provided !
i to initiate actions to mitigate the consequences of accidents that are beyond '
the ability of the operator to control. This specification provides the l OPERABILITY requirements, trip setpoints and response times that will ensure ,
i I
effectiveness of the systems to provide the design protection. Although the '
instruments are listed by system, in some cases the same instrument may be j used to send the actuation signal to more than one system at the same time.
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i DSERT XRSEKT F r
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LA SAltE - UNIT 1 B 3/4 3-2 AMENDMENT N). 98 e
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{ ATFACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS i
4 INSERT E For the sensors associated with MSIV isolation, instrumentation channels
- are not required to be response time tested. Response time testing for the
, remaining channel components, including any analog trip units, is required.
] This allowance is supported by NEDO-32291-A, " System Analyses for the Elimination of Selected Response Time Testing Requirements," October 1995.
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1 ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT F Per Note #, the ECCS actuation instrument channels are not required to be response time tested. The overall ECCS response time requirement, which ;
includes diesel generator injection valves, pumps, and other components, still j applies. This allowance is supported by .NEDO-32291-A, " System Analyses for the Elimination of Selected Response Time Testing Requirements," October 1995.
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i LA SALLE - UNIT 2 3/4 3-6 Amendment No. 6
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEfrECHNICAL SPECIFICATIONS l INSERT A (Proposed footnote for Table 3.3.1-2)
- Sensor is eliminated from response time testing for the RPS circuits.
Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.
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TABLE 3.3.2-3 i
l ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
)
! A. AUTOMATIC INITIATION
- 1. PRIMARY CONTAINMENT ISOLATION f -
Low, Level 3 1)
Low Low, Level 2 N/A 2)
Low Low Low, Level I N/A
- 3) s1.0*k
- b. Drywell Pressure - High
- c. N/A Main Steam Line ,
I) Radiation - High ") s1.0*M
- 2) Pressure - Low I s 2.0*8 1 Flow - High d.
3)
Main Steam Line Tunnel Temperature - High s
A
.5* f
- e. Condenser. Vacuum - Low N/A
- f. Main Steam Line Tunnel ATemperature - High N/A l 2. SECONDARY CONTAINMENT ISOLATION N/A
- a. Reactor Building Vent Exhaust Plenum Radiation - High
- b. Drywell Pressure - High ~
- c. Reactor Vessel Water Level - Low, Level 2 j d. Fuel Pool Vent Exhaust Radiation - High
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION N/A i a. AFlow - High
- b. Heat Exchanger Area Temperature - High
- c. Heat Exchanger Area Ventilation AT-High
- d. SLCS Initiation
- e. Reactor Vessel Water Level - Low Low, Level 2
- 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION N/A I a. RCIC Steam Line Flow - High i b. RCIC Steam Supply Pressure - Low
! c. RCIC Turbine Exhaust Diaphragm Pressure - High
! d. RCIC Equipment Room Temperature - High
- e. RCIC Steam Line Tunnel Temperature - High i f. RCIC Steam Line Tunnel ATemperature - High j g. Drywell Pressure - High
- h. RCIC Equipment Room ATemperature - High
! 5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION N/A
- c. RHR Heat Exchanger Steam Supply Flow High 1
LA SALLE - UNIT 2 3/4 3-18 AMENDMENT NO. 82
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (SecondsW ,
- 6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION N/A
- a. Reactor Vesse Water Level - Low, Level 3
) b. Reactor Vesse:
'.' (RHR Cut-In Permissive '
- c. RHR Pump Suction Flow -) HighPressure - High '
- d. RHR Area Cooler Temperature High
- e. RHR Equipment Area AT High j B. MANUAL INITIATION
- N/A i 1. Inboard Valves
- 2. Outboard Valves
- 3. Inboard Valves i 4. Outboard Valves
- 5. Inboard Valves
! 6. Outboard Valves
- 7. Outboard Valve TABLE NOTATIONS * -
i
- i Isolation system instrumentation response time for MSIVs only. No diesel generator delays assumed.
t from response t'me ttstin Res
- Radiationdetectorsareexem$oroutputorthe'nputofthe.
shall be measured from detec firskonsetime !
- electronic component in the channel. ,
Isolation system instrumentation response time specified for the Trip Function actuatino the MSIVs shall be added to MSLV isolation time to ,
obtain ISOLATION SYSTEM RESPONSE TIME for each va've.
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IN5%T P> \
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N/A Not Applicable.
LA SALLE - UNIT 2, 3/4 3-19 Amendment No. 87
)
i ATTACHMENT B PROPOSED AMENDMENTS TO THE i LICENSEffECHNICAL SPECIFICATIONS i
INSERT B '
(Proposed footnote for Table 3.3.2-3) I 1
4 l
- " Sensor is eliminated from response time testing for the MSIV actuation i logic circuits. Response time testing and conformance to the administrative i j limits for the remaining channel including trip unit and relay logic are
! required."
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TABLE 3.3.3-3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES ECEE RESPONSE TIME (Seconds)
- 1. LOW PRESSURE CORE SPRAY SYSTEM s60*/b
- 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Pumps A, B, and C) s60*fN ,
- 4. HIGH PRESSURE CORE SPRAY SYSTEM s'41
- 5. LOSS OF POWER NA
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- Injection valves shall be fully OPEN within 40 seconds after receipt of the reactor vessel pressure and ECCS Injection Line Pressure Interlock signal concurrently with power source availability and receipt of an accident initiation signal.
INSERTC LA SALLE - UNIT 2 3/4 3-31 Amendment No. SO
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT C (Proposed footnote for Table 3.3.3-3)
- "ECCS actuation instrumentation is eliminated from response time testing."
i i
4 B-4
I 3/4.3 INSTRUMENTATION t
BASES S
3 /4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:
- a. Preserve the integrity of the fuel cladding.
- b. Preserve the integrity of the reactor coolant system.
- c. Minimize the energy which must be adsorbed following a loss'-of-coolant accident, and
- d. Prevent inadvertent criticality., ,,,
l This specification provides the limiting conditions for operation I necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service l because of maintenance. When necessary, one channel may be made inoperable for brief intervals to conduct required surveillance.
The reactor protection system is made up of two independent trip systems, i There are usually four channels to monitor each parameter with two channels in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram. The system meets the intent of IEEE-279, 1971, for nuclear power plant protection systems. Specified surveillance intervals for MSIV-Closure, TSV-Closure, TCV-Closure, and the i
Manual Scram have been determined in accordance with NEDC-30851P-A, " Technical Specification Improvement Analyses for BWR Reactor Protection System" March l
1988. The bases for the trip settings of the RPS are discussed in the bases for Specification 2.2.1.
The measurement of response time at the specified frequencies provides assurance that the protective functions associated with eachc hannel=are c com-i 2
plated within the time limit assumed in the accident-analysis. No credit was
' taken for those channels with response times indicated as not applicable. l Response time may be demonstrated by any series of sequential, overlapping or '
total channel test measurement, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be
' ' demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
1 INSERT D 4
l l LA SALLE - UNIT 2 B 3/4 3-1 AMENDMENT NO. 79
}
i
)
i ATTACHMENT B l
PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS l
l INSERT D i
The measurement of response time at the specified frequencies provides j assurance that the protective functions associated with each channel are com-i pleted within the time limit assumed in the accident analysis. The RPS
! RESPONSE TIME acceptance criteria are included in plant Surveillance i procedures. Only those functions with times assumed in the accident analysis
! are required to be response time tested.
l As stated in Note
- of Table 3.3.1-2, Neutron detectors are exempt from response time testing. In addition, for Functional Units 3 and 4, per Note #,the
- associated sensors are not required to be response time tested. For these Functional Units, response time testing for the remaining channel components, j including any analog trip units, is required. This allowance is supported by
, NEDO-32291-A, " System Analyses for the Elimination of Selected Response
- Time Testing Requirements," October 1995.
! Response time may be demonstrated by any series of sequential, overlapping or 3
total channel test measurement, provided such tests demonstrate the total
! channel response time as defined. Sensor response time verification may be demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
l l
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t B-5
i INSTRUMENTATION l BASES i
j 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used j to mitigate the consequences of accidents by prescribing the OPERABILITY trip 4
setpoints and response times for isolation of the reactor systems. When I
necessary, one channel may be inoperable for brief intervals to conduct i
required surveillance. Both channels of each trip system for the main steam tunnel ambient temperature and ventilation system differential temperature may be placed in an inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required reactor
) building ventilation system maintenance and testing and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the j required secondary containment Leak Rate test without placing the trip system
- in the tripped condition. This will allow for maintaining the reliability of t
the ventilation system and secondary containment. Some of the trip settings may have tolerances explicitly stated where both the high and low values are j
critical and may have a substantial effect on safety. The setpoints of other instrumentation, where only the high or low and of the setting have a direct
{
bearing on safety, are established at a level away from the normal operating j range to prevent inadvertent actuation of the systems involved. !
Except for the MSIVs, the safety analysis does not address individual
! sensor response times or the response times of the logic systems to which the
- sensors are connected. For A.C. operated valves, it is assumed that the A.C.
power supply is lost and is restored by startup of the emergency diesel l generators. In this event, a time of 13 seconds is assumed before the valve j
starts to move. The safety analysis considers an allowable inventory loss l which in turn determines the valve speed in conjunction with the 13 second
- delay.
1 et '
3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION j
The emergency core cooling system actuation instrumentation is provided i to initiate actions to mitigate the consequences of accidents that are beyond the ability of the operator to control. This specification provides the OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection. Although the instruments are listed by system, in some cases the same instrument may be used to send the actuation signal to more than one system at the same time.
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^NSERT P
- 3SERTE i
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! LA SALLE - UNIT 2 8 3/4 3-2 AMEN 0HENT NO. 82 3
J
N ATTACHMENT B 4
PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS INSERT E For the sensors associated with MSIV isolation, instrumentation channels
] are not required to be response time tested. Response time testing for the i
remaining channel components, including any analog trip units, is required.
This allowance is supported by NEDO-32291-A, " System Analyses for the
! Elimination of Selected Response Time Testing Requirements," October 1995.
B-6
ATTACHMENT B PROPOSED AMENDMENTS TO THE i LICENSEffECHNICAL SPECIFICATIONS INSERT F 1
l Per Note #, the ECCS actuation instrument channels are not required to l be response time tested. The overall ECCS response time requirement, which includes diesel generator it.:jection valves, pumps, and other components, still applies. This allowance is t.upported by NEDO-32291-A, " System Analyses for l the Elimination of Selected Response Time Testing Requirements," October j 1995.
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ATTACHMENT C
- SIGNIFICANT HAZARDS CONSIDERATION l Commonwealth Edison 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 purpose of the proposed Technical Specification (TS) change is to
- eliminate response time testing requirements for selected components in the Reactor Protection System (RPS), Isolation Actuation instrumentation
! and Emergency Core Cooling System (ECCS) actuation instrumentation.
The Boiling Water Reactor Owners' Group (BWROG) has completed an evaluation which demonstrates that response time testing is redundant to the other TS-required testing. These other tests, in conjunction with actions taken in response to NRC Bulletin 90-01, " Loss of Fill-Oil in
! Transmitters Manufactured by Rosemount," and Supplement 1, are i
sufficient to identify failure modes or degradations in instrument response time and ensure operation of the associated systems within acceptable limits. There are no known failure modes that can be detected by response time testing that cannot also be detected by the other TS-required testing. This evaluation was documented in NEDO-32291-A,
" System Analyses for the Elimination of Selected Response Time Testing Requirements," dated October 1995. LaSalle County Station, LaSalle, has confirmed the applicability of this evaluation to LaSalle. In addition, LaSalle will complete the actions identified in the NRC staffs safety evaluation of NEDO-32291-A.
Because of the continued application of other existing TS-required tests such as channel calibrations, channel checks, channel functional tests, ,
and logic system functional tests, the response time of these systems will be maintained within the acceptance limits assumed in plant safety analyses and required for successful mitigation of an initiating event.
The proposed changes do not affect the capability of the associated systems to perform their intended function within their required response time, nor do the proposed changes themselves affect the operation of any equipment. As a result, LaSalle has concluded that the proposed changes do not involve a significant increase in the probability or the C-1
4 ATTACHMENT C i
l SIGNIFICANT HAZARDS CONSIDERATION consequences of an accident previously evaluated.
i i 2) Create the possibility of a new or different kind of accident from any j accident previously evaluated because:
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The proposed changes only apply to the testing requirements for the components identified above and do not result in any physical change to 4 these or other components or their operation. As a result no new failure 4
modes are introduced. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
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j 3) Involve a significant reduction in the margin of safety because:
l The current TS-required response times are based on the maximum l allowable values assumed in the plant safety analyses. These analyses
, conservatively establish the margin of safety. As described above, the
! proposed changes do not affect the capability of the associated systems to i perform their intended function within the allowed response time used as the basis for the plant safety analyses. The potential failure modes for the components within the scope of this request were evaluated for
- impact on instrument response time. This evaluation confirmed that, j with the exception of loss of fill-oil of Rosemount transmitters, the i remaining TS-required testing is sufficient to identify failure modes or
- degradations in instrument response times and ensure that operation of the applicable instrumentation is within acceptable limits. The actions i taken in response to NRC Bulletin 90-01 and Supplement 1 are adequate i
to identify loss of fill-oil failures of Rosemount transmitters. As a result,
- it has been concluded that plant and system response to an initiating event will remain in compliance with the assumptions of the safety
- analysis.
1 Further, although not explicitly evaluated, the proposed changes will provide an improvement to plant safety and operation by the following:
I a. Reducing the time safety systems are unavailable, i
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ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION
- b. Reducing the potential for safety system actuations,
- c. Reducing plant shutdown risk,
- d. Limiting radiation exposure to plant personnel, and
- e. Eliminating the diversion of key personnel resources to conduct j unnecessary testing.
Therefore, LaSalle has concluded that this request will not significantly l reduce the margin of safety, and may actually cause an increase in the i
margin of safety. i i !
- Guidance has been provided in " Final Procedures and Standards on No !
- Significant Hazards Considerations," Final Rule,51 FR 7744, for the application '
, of standards to license change requests for determination of the existence of i significant hazards considerations. This document provides examples of j amendments which are and are 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 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 Standard Review Plan. This proposed amendment does not involve a 4
significant relaxation of the criteria used to establish safety limits, a significant i relaxation of the bases for the limiting safety system settings or a significant 4
relaxation of the bases for the limiting conditions for operations. Therefore, J 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 l significant hazards consideration. i i
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ATTACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW !
Commonwealth Edison has evaluated the proposed amendment against the I
- criteria for identification of licensing and regulatory actions requiring i 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 j considerations or do not involve a significant increase in the amounts, and no
! significant changes in the types of any effluents that may be released off-site.
Additionally, this request does not involve a significant increase in individual or cumulative occupational radiation exposure.
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ATTACHMENT E
- LARAY T.R COUNTY STATION INSTRUMENTATION LOOP COMPONENTS
! RTT TRIP FUNCTION TABLE NO: 3.3.1-2 i RTT TRIP FUNCTION ITEM NO: 3.
! SYSTEM DESCRIPTION: Reactor Protection System Response Times
! TRIP FUNCTION DESCRIPTION: Rx Vessel Steam Dome Pressure - High
- T.S. RTT REQUIREMENT (Secs)
- Less than or eaual to 0.55 l DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
Pressure Switch Senses Reactor Steam B21-N023AA,
, Dome Pressure and trips on Static-O-Ring; 4
High Pressure. 9N6-B45-NX-C1A-JJITX6 RPS scram Relay De-energizes Scram C71A-K5A; GE HFA i Contactors C71A-K14A & l C71A-K14E.
Scram Contactors De-energizes the Scram C71 A-K14A, E; Solenoids. CR105 or CR305 i
Reference Drawing Numbers: -
1E-1-4215AC, Rev. AH 1E-1-4215AH, Rev. L E-1
ATTACHMENT E LASAT.TR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.1-2 __
RTT TRIP FUNCTION ITEM NO: 4.
SYSTEM DESCRIPTION: Reactor Protection System Response Times TRIP FUNCITON DESCRIIrrION: Reactor Vessel Water Level - Low. Level 3 T.S. RTT REQUIREMENT (Secs): Less than or eaual to 1.05 DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
Level Transmitter Senses Reactor Water Level. B21-N403A, Rosemount 1153 Master Trip Unit Provides trip signal for RPS B21-N703A, (MTU) on Reactor Water Level Low Rosemount 710DU Level - 3.
MTU Output Relay De-energizes relav B21-K104A, C71A-K6A. Agastat EGPB RPS Scram Relay De-energizes Scram C71A-K6A, Contactors C71A-K14A & GE HFA C71A-K14E.
Scram Contactom De-energizes the Scram C71 A-K14A, E; Solenoids. CR105 or CR305 Reference Drawing Numbem: -
1E-1-4215AC, Rev. AH 1E-1-4215AH, Rev. L 1E-1-4232AW, Rev. B E-2
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l 4 i ATTACHMENT E LASAT.IR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS i
RTT TRIP FUNCTION TABLE NO: 3.3.2-3 l
! RTF TRIP FUNCTION ITEM NO: A.1.a.3) i SYSTEM DESCRIPTION: Isolation sys. Instrumentation Response Time
{ TRIP FUNCTION DESCRIPTION: Rx Vessel Water Level Low Low Low. Level 1
. T.S. RTT REQUIREMENT (Secs): Less than or equal to 1.0*
l DESCRIPTION OF FUNCTION DEVICE i
, COMPONENT EPN & MODEL # !
- l l Level- 1 Transmitter Senses level and provides B21-N402A l l analog signal to MTU. Rosemount 1153
- Master Trip Unit Trips at preset value to de- B21-N702A ;
(MTU) energize the output relay. Rosemount 710DU MTU Output Relay De-energizes Relay B21-K100A l B21H-K6A on Reactor Agastat EGPB Water Level below Level - 1.
Interfacing Relay De-energizes Relays B21H- B21H-K7A K16 and B21H-K51. GE HFA Initiation Relay De-energizes to close B21H-K16 Outboard MSIVs.* GE HFA Initiation Relay De-energizes to close B21H-K51 Inboard MSIVs.* GE HFA j
- Isolation system instrumentation response time for MSIVs only.
Reference Drawing Numbers: -
1E-14232AB, Rev. X 1E-1-1232AU, Rev. C 1E-1-4203AB, Rev. T 1E-1-4203AF, Rev. W E-3
ATTACHMENT E LASALLE COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.2-3
. RTF TRIP FUNCTION ITEM NO: A.1.c.D j SYSTEM DESCRIFFION: Isolation Sys. Instrumentation Response Time TRIP FUNCTION DESCRIITION: Main Steam Line Radiation - High
! T.S. RTT REQUIREMFNT (Secs): Less than or eaual to 1.0*
DESCRIFFION OF FUNCTION DEVICE l 1
COMPONENT EPN & MODEL #
! Gamma Ion Chamber Senses Radiation level & D18-N003A, l Steam Line Detector
- outputs to Log Radiation GE 1
Monitor.
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4 Log Radiation De-energizes Relay D18-K610A, Monitor C51-K73/Z2A GE, 4 Output Relay De-energizes Relay C51-K73/Z2A, C71A-K7A GE Z2 Aux Trip Unit
! Interfacing Relay De-energizes Relay B21H- C71A-K7A, j K8A GE HFA Initiation Relay De-energizes Relay B21H- B21H-K8A,
i Initiation Relay Closes outboard MSIVs.** B21H-K16, GE HFA i Initiation Relay Closes inboard MSIVs.** B21H-K51, GE HFA i ' Radiation Detectors are exempt from Response Time Testing.
" MSIVs Close on one-out-of two twice logic.
Reference Drawing Numbers:
1E-1-4218AE, Rev. F
E-4 1
A'ITACHMENT E LASAY>IR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS 4
l RTT TRIP FUNCTION TABLE NO: 3.3.2-3 RTT TRIP FUNCTION ITEM NO: A.1.c.2)
, SYSTEM DESCRIPTION: Isolation Sys. Instrumentation Response Time
! TRIP FUNCTION DESCRIPTION: Main Steam Line Pressure - Low T.S. RTT REQUIREMENT (Secs): Less than or equal to 2.0*
4 I
DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
- Pressure Switch Senses pressure in MSL and B21-N015A,
! de-energizes relay B21H- Static-O-Ring, K4A on low pressure to 9N6-B45-C1A-JJITX6
- initiate isol ation
} Interfacing Relay De-energizes Relay B21H- B21H-K4A, K7A GE HFA Initiation Relay De-energizes Relays B21H- B21H-K7A,
! GE HFA l Initiation Relay Closes inboard MSIVs.* B21H-K51, GE HFA
- MSIVs Close on one-out-of two twice logic.
Reference Drawing Numbers:
1E-1-4232AB, Rev. X 1E-1-4203AB, Rev. T 1E-1-4203AF, Rev. W l
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] ATTACHMENT E LASAT.YR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS 1
RTT TRIP FUNCTION TABLE NO: 3.3.2-3 RTT TRIP FUNCTION ITEM NO: A.1.c.3)
SYSTEM DESCRIPTION: Isolation Sys. Instrumentation Response Time TRIP FUNCTION DESCRIPTION: Main Steam Line Flow - High
, T.S. RTT REQUIREMENT (Secs): Less than or eaual to 0.5*
DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
Differential Pressure Senses MSL flow and B21-N008A through 9A, Switch de-energizes relay B21H- Static-O-Ring, j
. K3A on high flow to 102AS-B035-NX-C1A- l l initiate isolation JJITX6 i l
Interfacing Relay De-energizes Relay B21H-K3A, !
Initiation Relay De-energizes Relays B21H-K7A, l
, B21H-K16 and B21H-K51 GE HFA
! Initiation Relay Closes outboard MSIVs.* B21H-K16,
- GE HFA
! I
, Initiation Relay Closes inboard MSIVs.* B21H-K51, j GE HFA l 1
- MSIVs Close on one-out-of two twice logic.
1 Reference Drawing Numbers: l 1E-1-4232AB, Rev. X i 1E-1-4203AB, Rev. T l 1E-1-4203AF, Rev. W I
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ATTACHMENT E LASAT YR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3 3 (1 of 2)
RTT TRIP FUNCTION ITEM NO: 1. & 2.
SYSTEM DESCRIPTION: Low Pressure Core Sorav/A RHR(LPCI mode)
TRIP FUNCTION DESCRIIYrION: Rx Vessel Water Level Low Low Low. Level 1 T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
Level Transmitter Senses level and provides B21-N407A, C analog signal to MTU. Rosemount 1154 Master Trip Unit Trips at preset value to B21A-N707A, C 3 (MTU) Energize the output relay. Rosemount 710DU i MTU Output Relay Energizes Relay E21A-K2, B21A-K707AX, CX E21A-K3 on Reactor Water Agastat EGPB Level below Level - 1. j Initiation Relay Energizes Relay E21A-K10 E21 A-K2, E21A-K3 !
based on Drywell High GE HFA Pressure & Rx Low Level l Logic. j Initiation Relay Energizes E12A-K98A and E21A-K10 E12A-K9A to initiate logic to GE HFA l start 0 diesel generator and RHR A. Energizes E21A-K12 ,
to provide a permissive to l start LPCS if power is !
available. Energizes E21A- i K14 to open LPCS Injection valve if rx pressure is low and power is available. ,
Initiation Relay Energizes to interlock the E21A-K12 start of LPCS. GE HMA E-7
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l l ATTACHMEVr E LASAT YR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3 3 (2 of 2) l
, RTT TRIP FUNCTION ITEM NO: 1 & 2.
SYSTEM DESCRIPTION: Low Pressure Core Sorav/A RHRR.PCI mode)
TRIP FUNCTION DESCRIPTION: Rx Vessel Water Level Low Low Low. Level 1 T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
a DESCRIPTION OF FUNCTION DEVICE l COMPONENT EPN & MODEL # q l
Initiation Relay Energizes to open LPCS E21A-K14 Injection valve, E21-F005. GE HMA Initiation Relay Energizes E12A-K70A to E12A-K9A provide permissive to start GE HFA A RHR if power is available.
Energizes E12A-K23A to open A RHR Injection valve if rx pressure is low and power is available.
Initiation Relay Energizes to start E12A-K70A # I A RHR after 5 second time Agastat delay 145C3217P058 Initiation Relay Energizes to open A RHR E12A-K23A Injection valve, E12-F042A. GE HMA i Initiation Relay Energizes to initiate start of E12A-K98A
- the 0 diesel generator. GE HFA i
- Injection valves shall be fully OPEN within 40 seconds after receipt of the reactor vessel pressure and ECCS Injection Line Pressure Interlock signal concurrently with power source availability and receipt of an accident initiation i signal. l i # Time delay relay response time is performed by calibration.
Reference Drawing Numbers:
1E-1-4200ZC, Rev. B 1E-1-422.1 AIT, Rev. U 1E-1-4220AH, Rev V E-8
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ATTACHMENT E i LASAT TR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS l
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RTF TRIP FUNCTION TABLE NO: 3.3.3-3 (1 OF 2)
RTT TRIP FUNCTION ITEM NO: 1. & 2.
- SYSTEM DESCRIPTION
- Low Pressure Core Sorav/A RHR1PCI mode)
TRIP FUNCTION DESCRIPTION: Drywell Pressure -High T.S. RTF REQUIREMENT (Secs): Less than or eaual to 60*
i DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL # l i Differential Pressure Senses drywell pressure and B21-N048A, C i Switch energizes relays E21A-K4 Static-O-Ring l' and E21A-K5 on high 12N6-B4-NX-C1A-drywell pressure. JJTrX7 I Initiation Relay Energizes Relay E21A-K10 E21 A-K4, E21 A-K5
, based on Drywell High GE HFA Pressure & Rx Low Level Logic.
Initiation Relay Energizes E12A-K98A and E21A-K10
.: E12A-K9A to initiate logic to GE HFA 2
start 0 Diesel Generator and RHR A. Energizes E21A-K12
- to provide a permissive to start LPCS pump if power is available. Energizes E21A-K14 to open LPCS Injection valve if rx pressure is low j and power is available.
Initiation Relay Energizes to interlock the E21A-K12 i start of LPCS pump. GE HMA l Initiation Relay Energizes to open LPCS E21A-K14 Injection valve, E21-F005. GE HMA i
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ATTACHMENT E LASALLE COUNTY STATION INSTRUlWENTATION LOOP COMPONENTS RTF TRIP FUNCTION TABLE NO: 3.3.3-3 (2 O F 2)
RTT TRIP FUNCTION ITEM NO: 1. & 2.
SYSTEM DESCRIPTION: Low Pressure Core Soray/A RHR(LPCI mode)
TRIP FUNCTION DESCRIPTION: Drywell Pressure -High T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL Initiation Relay Energizes E12A-K70A to E12A-K9A 4
provide permissive to start GE HFA q A RHR pump if power is l available. Energizes E12A-K23A to open A RHR Injection valve if rx pressure 3 is low and power is
- available.
! Initiathn Relay Energizes to start E12A-K70A#
A RHR after 5 second time Agastat delay 145C3217P058 i; Initiation Relay Energizes to open A RHR E12A-K23A
. Injection valve, E12-F042A. GE HMA
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- Injection valves shall be fully OPEN within 40 seconds after receipt of the
! reactor vessel pressure and ECCS Injection Line Pressure Interlock signal
! concurrently with power source availability and receipt of an accident initiation j signal.
! Time delay relay response time is per'ormed by calibration.
4
- Reference Drawing Numbers
! 1E-1-4221AD, Rev. U 1E-1-4220AH, Rev. V i
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LAMAT.T.R COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTF TRIP FUNCTION TABLE NO: 3.3.3-3 (1 of 2)
RTT TRIP FUNCTION ITEM NO: 2.
SYSTEM DESCRIlmON: Residual Heat Removal ** (RHR) B & C I TRIP FUNCTION DESCRIPTION: Rx Vessel Water Level-Low Low Low. Level 1 l T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
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- DESCRIPTION OF FUNCTION DEVICE i COMPONENT EPN & MODEL #
l Level Transmitter Senses level and provides B21-N407B, D
! analog signal to MTU. Rosemount 1154 4
! Master Trip Unit Trips at preset value to B21A-N707B, D l (MTU) Energize the output relay. Rosemount 710DU
- i l MTU Output Relay Energizes Relay E12A-K7, B21A-K707BX, DX l 1 E12A-K8 on Reactor Water Agastat EGPB i Level below l Level - 1.
1 i Initiation Relay Energizes Relays E12A-K9B, E12A-K7 and i E12A-K98B and E12A-K94B E12A-K8 j based on Drywell High GE HFA L Pressure & Rx Low Level
! Logic.
I j Initiation Relay Energizes E12A-K21 to E12A-K94B
! provide a permissive to start GE HFA i RHR C pump if power is
! available. Energizes E12A-
! K25 to open RHR C
- Injection valve if rx pressure is low and power is j available.
l Initiation Relay Energizes to interlock the E12A-K21 1, start of RHR C pump. GE HMA a
l Initiation Relay Energizes to open RHR C E12A-K25 j Injection valve, E12-F042C. GE HMA i
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ATTACHMENT E LASALLE COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCITON TABLE NO: 3.3.3-3 (2 of 2)
RTT TRIP FUNCTION ITEM NO: 1. & 2.
SYSTEM DESCRIPTION: Residual Heat Removal ** (RHR) B & C TRIP FUNCTION DESCRIPTION: Rx Vessel Water Level Low Low Low. Level 1 l T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
1 i DESCRIFFION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
l Initiation Relay Energizes E12A-K70B to E12A-K9B i provide permissive to start GE HFA j RHR B if power is available.
l Energizes E12A-K23B to j open RHR B Injection valve
- if rx pressure is low and l power is available.
Initiation Relay Energizes to start E12A-K70B #
l RHR B after 5 second time Agastat
- delay 145C3217P058 Initiation Relay Energizes to open RHR B E12A-K23B j Injection valve, E12-F042B. GE HMA
) Initiation Relay Energizes to initiate start of E12A-K98B
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the diesel generator A. GE HFA
! ' Injection valves shall be fully OPEN within 40 seconds after receipt of the i reactor vessel pressure and ECCS Injection Line Pressure Interlock signal
- concurrently with power source availability and receipt of an accident initiation signal.
i ** Low Pressure Coolant Injection (LPCI) mode
- Time delay relay response time is performed by calibration.
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Reference Drawing Numbers:
- 1E-1-4200ZD, Rev. B
! 1E-1-4220AK, Rev. X j 1E-1-4220AL, Rev. S i
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, ATTACHMENT E j LASAIJR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3-3 (1 of 2)
RTT TRIP FUNCTION ITEM NO: 2.
! SYSTEM DESCRIPTION: Residual Heat Removal" (RHR) B & C l i TRIP FUNCTION DESCRIPTION: Dmvell Pressure - High j T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
! DESCRIPTION OF FUNCTION DEVICE l COMPONENT EPN & MODEL #
j Differential Pressure Senses drywell pressure and B21-N048B, D i- Switch energizes relays E12A-K5 Static-O-Ring j and E12A-K6 on high 12N6-B4-NX-C1A- :
l drywell pressure. JJTTX7 l l Initiation Relay Energizes Relays E12A-K9B, E12A-K5 and
! Logic.
! Initiation Relay Energizes E12A-K21 to E12A-K94B provide a permissive to start GE HFA RHR C pump if power is available. Energizes E12A-t K25 to open RHR C Injection valve if rx pressure is low and power is
- available.
! Initiation Relay Energizes to interlock the E12A-K21
Initiation Relay Energizes to open RHR C E12A-K25 Injection valve, E12-F042C. GE HMA i
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1 ATTACHMENT E LASAT IR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3-3 (2 of 2)
- RTT TRIP FUNCTION ITEM NO: 2. !
. SYSTEM DESCRIITION: Residual Heat Removal ** (RHR) B & C TRIP FUNCTION DESCRIFFION: Drywell Pressure - High T.S. RTT REQUIREMENT (Secs): Less than or eaual to 60*
DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
i Initiation Relay Energizes E12A-K70B to E12A-K9B
! Energizes E12A-K23B to j open RHR B Injection valve if rx pressure is low and power is available.
! Initiation Relay Energizes to start E12A-K70B # l
- RHR B after 5 second time Agastat delay 145C3217P058 i
Initiation Relay Energizes to open RHR B E12A-K23B Injection valve, E12-F042B. GE HMA Initiation Relay Energizes to initiate start of E12A-K98B the diesel generator A. GE HFA
- Injection valves shall be fully OPEN within 40 seconds after receipt of the i
reactor vessel pressure and ECCS Injection Line Pressure Interlock signal concurrently with power source availability and receipt of an accident initiation signal.
- Low Pressure Coolant Injection (LPCI) mode.
- Time delay relay response time is performed by calibration.
4 Reference Drawing Numbers:
1E-1-4220AK, Rev. X 1E-1-4220AL, Rev. S 1
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l ATTACHMENT E LASAI.IR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3-3 (1 of 2) i RTT TRIP FUNCTION ITEM NO: 4.
SYSTEM DESCRIPTION: High Pressure Core Sprav (HPCS)
TRIP FUNCTION DESCRIPTION: Rx Vessel Water Level-Low Low Level 2 T.S. RTT REQUIREMENT (Secs): Less than or equal to 41 l DESCRIPTION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
Level Transmitter Senses level and provides B21-N406A, & C l analog signal to MTU. Rosemount 1154 Master Trip Unit Trips at preset value to B21A-N706A & C, l (MTU) Energize the output relay. Rosemount 710DU
- MTU Output Relay Energizes Relay E22A-K7, B21A-K706AX & CX E22A-K8 on Reactor Water Agastat EGPB
- Level below Level - 2.
Initiation Relay Energizes Relays E22A-K3 E22A-K7 and K8 and E22A-K9 based on GE HFA Drywell High Pressure & Rx j Low Level Logic.
Initiation Relay Energizes E22B-K14 to E22A-K3
- provide a permissive to start GE HFA HPCS pump if power is available. Energizes to provide start permissive to the B diesel generator l E-15
4 ATTACHMENT E LASAT YR COUNTY STATION INSTRUMENTATION LOOP COMPONENTS RTT TRIP FUNCTION TABLE NO: 3.3.3-3 (2 of 2) i RTT TRIP FUNCTION ITEM NO: 4.
SYSTEM DESCRIFFION: High Pressure Core Sorav GIPCS)
- TRIP FUNCTION DESCRIFFION
- Rx Vessel Water Level-Low Low Level 2 l j T.S. RTT REQUIREMENT (Secs): Less than or eaual to 4I l
- l DESCRIPTION OF FUNCTION DEVICE l COMPONENT EPN & MODEL #
! Initiation Relay Energizes to provide a E22B-K14 1
permissive to start the GE HMA 3 HPCS pump if power is l available.
? Initiation Relay Energizes to open HPCS E22A-K9
- Injection valve E22-F004, if GE HFA
! rx pressure is low, f
! Reference Drawing Numbers:
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1E-1-4223AE, Rev. P i 1E-1-4223AH, Rev. V i
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, ATTACHMENT E
- LASALLE COUNTY STATION INSTRUMENTATION LOOP COMPONENTS
- RTT TRIP FUNCTION TABLE NO
- 3.3.3-3
- RTT TRIP FUNCTION ITEM NO: 4.
SYSTEM DESCRIPTION: High Pressure Core Soray (HPCS)
> TRIP FUNCTION DESCRIPTION: Drywell Pressure - High j T.S. RTF REQUIREMENT (Secs): Less than or eaual to 41
! DESCRIFFION OF FUNCTION DEVICE COMPONENT EPN & MODEL #
! Differential Pressure Senses drywell pressure and B21-N047A & C, Switch energizes relays E22A-K5 Static-O-Ring l and E22A-K6 on high 12N6-B4-NX-C1A-l drywell pressure. JJTFX7
. Initiation Relay Energizes Relays E22A-K3 E22A-K5 and i and E22A-K9 based on E22A-K6 j Drywell High Pressure & Rx GE HFA i
Low Level Logic.
Initiation Relay Energizes E22B-K14 to E22A-K3
~
j provide start permissive to l the B diesel generator 1
Initiation Relay Energizes to provide a E22B-K14 permissive to start the GE HMA l HPCS pump if power is
- available.
Initiation Relay Energizes to open HPCS E22A-K9
- Injection valve E22-F004, if GE HFA i rx pressure is low.
l Reference Drawing Numbers:
- j 1E-1-4223AH, Rev. V
! E-17 i
I