ML20141H798
| ML20141H798 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/29/1997 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141H801 | List: |
| References | |
| NUDOCS 9708010183 | |
| Download: ML20141H798 (18) | |
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
.o WASHINGTON, D.C. 2005H001 COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendm'ent filed by the Commonwealth Edison Company (the licensee), dated April 14, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
9708010183 970729 PDR ADOCK 05000373 P
Q (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised 4
through Amendment No.119, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
i-The licensee shall operate.the facility in accordance with the Technical Specifications and the Environmental Protection Plan 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/&
Donna M. Skay, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 29, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT l
3/4 3-86 3/4 3-86 1
3/4 3-87 3/4 3-87 B 3/4 3-4 B 3/4 3-4 B 3/4 3-4a B 3/4 3-4a B 3/4 3-6 B 3/4 3-6 B 3/4 3-6a
INSTRUMENTATION 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING, CONDITION FOR OPERATION 3.3.8 fi.a feedwater/ main turbine trip system actuation instrumentation i
channels shown in Table 3.3.8-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
{
a.
With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.8-2, declare the channel inoper-able until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more channels required by Table 3.3.8-1 inoperable:
1.
Within j hours, verify sufficient channels remain OPERABLE or tripped to maintain trip capability, and 2.
Within 7 days, either place the inoperable channel (s) in the trip system in the tripped
- condition or restore the inoperable channel (s) to OPERABLE status, c.
Otherwise, be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i SURVEILLANCE REQUIREMENTS i
4.3.8.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.8.1-1.
4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
l
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
LASALLE - UNIT 1 3/4 3-86 Amendment No.119
TABLE 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE CHANNELS TRIP FUNCTION PER TRIP SYSTEM a.
Reactor Vessel Water Level-High, level 8 4*
- A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance testing without placing the Trip System in the tripped condition.
LASALLE - UNIT 1 3/4 3-87 Amendment No.119 t
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INSTRUMENTATION BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION
[
The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-2-A, " Addendum To Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications (BWR RCIC Instrumentation)," December 1992. When a channel is placed in an inoperable i
status solely for performance of required surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains RCIC initiation capability.
An auxiliary relay contact of Channel A of the RCIC Reactor Vessel water Level - High, Level 8 instrumentation channel is used as an input to trip 4
Channel C of the Feedwater/ Main Turbine Trip System Actuation Instrumentation.
Therefore, the Limiting Condition for Operation and Surveillance Requirements of both TS 3/4.3.5 and 3/4.3.8 are applicable to the RCIC level 8 channel A instrumentation channel.
3/4.3.6 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the require-ments of the specifications in Section 3/4.1.4, Control Rod Program Controls.
The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P-A, Supplement 1,
" Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," October 1988, and GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected i
Instrumentation' Technical Specifications," December 1992. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains Control Rod Block capability.
3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that:
(1) the radiation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded, j
1 LA SALLE - UNIT 1 B 3/4 3-4 Amendment No. 119
INSTRUMENTATION BASES i
3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION (Continued)
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-1-A, " Bases for i
Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical SpeciTications," December 1992. When a l
channel is placed in an inoperable status solely for performance of required i
surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains initiation capability.
3.4.3.7.2 DELETED 3/4.3.7.3 METEOROLOGICAL MOMTORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures i
that sufficient meteorological data is availpble for estimating potential I
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 of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 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 from locations outside of the tantrol 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.
LA SALLE - UNIT 1 B 3/4 3-4a Amendment No.119 i
INSTRUMENTATION BASES 3/4.3.7.10 DELETED E L 7.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation provides for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup 1
system.
3/4.3.7.12 LOOSE-PART DETECTION SYSTEM
}
The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide I.133, " Loose-Part Detection Program for.the Primary System of Light-Water-Cooled Reactors."
3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is i
provided to initiate the feedwater system / main turbine trip system in the i
event of reactor vessel water level equal to or greater than the level 8 setpoint associated with a feedwater controller failure, to prevent overfilling the reactor vessel which may result in high pressure liquid discharge through the safety / relief valve discharge lines. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," December 1992. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LC0 and required ACTIONS may be delayed, provided the associated function maintains Feedwater System / Main Turbine Trip System l
actuation capability.
The four instrument channels are arranged to make a two out of three trip logic.
In order to eliminate the loss of the reactor vessel water level eight trip due to the loss of either variable leg instrument line for narrow range
)
level instrumentation, trip channel C of the level 8 trip logic cntains two reactor vessel water level 8 sensor trip relay contacts. Therefore, trip channel C contains two channels, providing the redundancy needed to prevent a failure to trip of the feedwater pumps / main turbine due to an instrument line failure. One of the four channels (one of the two channels in trip channel C) is from the Channel A RCIC reactor vessel water level 8 trip relay, which is associated with TS 3.3.5, Reactor Core Isolation Cooling System Actuation Instrumentation.
Actions b.1 and b.2 are modified by a Note that states that an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. This note acknowledges that an orderly shutdown per Action c is preferred to the transient that will occur if the trip were actuated.
LA SALLE - UNIT 1 B 3/4 3-6 Amendment No. 119
INSTRUMENTATION BASES 3/4.3.8 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION I
i INSTRUMENTATION (Continued)
Action b.1 assures that whatever combination of channels are inoperable, that automatic trip capability either exists or is restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, which is sufficient for the operator to take corrective action and takes into 4
account the likelihood of an event requiring actuation of this Trip Function.
This will require a minimum of two channels Operable or one channel Operable with one channel in the tripped condition in order to satisfy Action b.1.
If Action b.1 is satisfied, then Action b.2 is entered.
If Action b.1 is not satisfied, then Action c must be entered.
Action b.2 assures that each inoperable channel is placed in the tripped j
condition within 7 days.
If each inoperable channel is in the tripped condition or declared Operable within 7 days, then continued unit operation is 1
allowed, due to the remaining redundancy for single instrument failure.
If ene or more channels are inoperable, and cannot be placed in the tripped condition or declared Operable within 7 days, then Action c must be entt.i An auxiliary relay contact of Channel A of the RCIC Reactor Vessel Water Level - High, Level 8 instrumentation channel is used as an input to trip Channel C of the Feedwater/ Main Turbine Trip System Actuation Instrumentation.
Therefore, the Limiting Condition for Operation and Surveillance Requirements of both TS 3/4.3.5 and 3/4.3.8 are applicable to the RCIC level 8 channel A i
instrumentation channel.
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I LA SALLE - UNIT 1 B 3/4 3-6a Amendment No.119
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- pe UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066H001 L
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated April 14, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in j
10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized J
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follovs:
' (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.104, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION uud Y '
Donna M. Skay, Project Kanager Project Directorate III-2 Division of Reactor Projects - III/IV 4
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 29,1997 i
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ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 3-86 3/4 3-86 3/4 3-87 3/4 3-87 B 3/4 3-4 B 3/4 3-4 a
B 3/4 3-4a B 3/4 3-4a B 3/4 3-6 B 3/4 3-6
)
B 3/4 3-6a 1
)
J i
i
INSTRUMENTATION 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The feedwater/ main turbine trip system actuation instrumentation i
channels shown in Table 3.3.8-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
a.
With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.8-2, declare the channel inoper-able until the channel is restored to OPERABLE status with its trip 1
setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more channels required by Table 3.3.8-1 inoperable:
1.
Withinyhours,verifysufficientchannelsremainOPERABLEor tripped to maintain trip capability, and 2.
Within 7 days, either place the inoperable channel (s) in the trip system in the tripped
- condition or restore the inoperable channel (s) to OPERABLE status.
j c.
Otherwise, be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE0UIREMENTS 4.3.8.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations at the frequencies shown in Table 4.3.8.1-1.
4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
- An inoperable channel need not be placed in the trip' ped condition where this would cause the Trip Function to occur.
LA SALLE - UNIT 2 3/4 3-86 Amendment No.104
TABLE 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE CHANNELS TRIP FUNCTION PER TRIP SYSTEM a.
Reactor Vessel Water Level-High, Level 8 4*
i i
- A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance testing without placing the Trip System in the tripped condition.
LASALLE - UNIT 2 3/4 3-87 Amendment No.104 i
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INSTRUMENTATION BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING $fSTEM ACTUATION INSTRUMENTATION The reactor core isolation coo:ing system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of i
reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.
Specified surveillance intervals and surveillance and maintenance outage j
times have been determined in accordance with GENE-770-06-2-A, " Addendum To Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications. (BWR RCIC l
Instrumentation)," December 1992. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LC0 and 4
i required ACTIONS may be delayed, provided the associated function maintains 1
RCIC initiation capability.
An auxiliary relay contact of Channel A of the RCIC Reactor Vessel Water Level - High, level 8 instrumentation channel is used as an input to trip Channel C of the Feedwater/ Main Turbine Trip System Actuation Instrumentation.
Therefore, the Limiting Condition for Operation and Surveillance Requirements i
of-both T5 3/4.3.5 and 3/4.3.8 are applicable to the RCIC level 8 channel A j
instrumentation channel.
3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION i
The control rod block functions are provided consistent with the require-(
ments of the specifications in Section 3/4.1.4, Control Rod Program Controls.
l The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.
i j
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P-A, Supplement 1,
" Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," October 1988, and GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications," December 1992. When a channel is 4
4 placed in an inoperable status solely for performance of required i
surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains Control Rod Block capability.
3/4.3.7 MONITORING INSTRUMENTATION l
3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that:
(1) the radiation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
LA SALLE - UNIT 2 B 3/4 3-4 Amendment No. 104
INSTRUMENTATION BASES 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION (Continued)
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications," December 1992. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LC0 and required ACTIONS may be delayed, provided the associated function maintains initiation capability.
3.4.3.7.2 DELETED 3/4.3.7.3 NETEOR0 LOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data 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 of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 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 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.
'h'$
LA SALLE - UNIT 2 B 3/4 3-4a Amendment No.104
. ~. _
INSTRUMENTATION BASES f
3/4.3.7.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION
)
This instrumentation provides for monitoring (and controlling) the l
concentrations of potentially explosive gas mixtures in the waste gas holdup system.
3/4.3.7.12 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that 1
sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable.out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors."
3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION l
The feedwater/ main turbine trip system actuation instrumentation is provided to initiate the feedwater system / main turbine trip system in the i
event of reactor vessel water level equal to or greater than the level 8 i
setpoint associated with a feedwater controller failure, to prevent i
overfilling the reactor vessel which may result in high pressure liquid
{
discharge through the safety / relief valve discharge lines. Specified surveillance intervals and surveillance and raintenance outage times have been determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," December 1992. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LC0 and required ACTIONS may be delayed, provided the associated function maintains Feedwater System / Main Turbine Trip System actuation capability.
The four instrument channels are arranged to make a two out of three trip logic.
In order to eliminate the loss of the reactor vessel water level eight i
trip due to the loss of either variable leg instrument line for narrow range 1evel instrumentation, trip channel C of the level 8 trip logic contains two reactor vessel water level 8 sensor trip relay contacts. Therefore, trip channel C contains two channels, providing the redundancy needed to prevent a failure to trip of the feedwater pumps / main turbine due to an instrument line failure. One of the four channels (one of the two channels in trip channel C) is from the Channel A, RCIC reactor vessel water level 8 trip relay, which is associated with TS 3.3.5, Reactor Core Isolation Cooling System Actuation Instrumentation.
Actions b.1 and b.2 are modified by a Note that states that an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. This note acknowledges that an orderly shutdown per Action c is preferred to the transient that will occur if the trip were actuated.
1 l
LA SALLE - UNIT 2 B 3/4 3-6 Amendment No.104 l
IRSIRUMERTATION BASES i
3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION (Continued)
Action b.1 assures that whatever combination of channels are inoperable, that automatic trip capability either exists or is restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, which is sufficient for the operator to take corrective action and takes into account the likelihood of an event requiring actuation of this Trip Function.
This will require a minimum of two channels Operable or one channel Operable with one channel in the tripped condition in order to satisfy Action b.l.
If i
Action b.1 is satisfied, then Action b.2 is entered.
If Action b.1 is not i
satisfied, then Action c must be entered.
Action b.2 assures that each inoperable channel is placed in the tripped condition within 7 days.
If each inoperable channel is in the tripped condition or declared Operable within 7 days, then continued unit operation is allowed, due to the remaining redundancy for single instrument failure.
If one or more channels are inoperable, and cannot be placed in the tripped condition or declared Operable within 7 days, then Action c must be entered.
An auxiliary relay contact of Channel A of the RCIC Reactor Vessel Water Level - High, Level 8 instrumentation channel is used as an input to trip 1
Channel C of the Feedwater/ Main Turbine Trip System Actuation Instrumentation.
Therefore, the Limiting Condition for Operation and Surveillance Requirements of both TS 3/4.3.5 and 3/4.3.8 are applicable to the RCIC level 8 channel A instrumentation channel.
i LA SALLE - UNIT 2 8 3/4 3-6a Amendment No.104