ML17158A763
| ML17158A763 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/11/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158A764 | List: |
| References | |
| NPF-14-A-148, NPF-22-A-118 NUDOCS 9507180316 | |
| Download: ML17158A763 (30) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&N01 PENNSYLVANIA POW R
Ilt IGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
>48 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Im Light Company, dated April 10,
- 1995, 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 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:
(i) 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.
i 9507180315 950711 PDR ADGCK 05000387 P
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2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
>48 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n
. Stolz, Dire or roject Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July ll, 1995
aP ATTACHMENT TO LICE SE AM NDMENT NO, 148 FACILITY OPERATING LICENSE NO.
NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE XX11 3/4 3-1 3/4 3-6 3/4 3-9 3/4 3-10 3/4 3-21 3/4 3-22 3/4 3-27 3/4 3-33 QS~R XX11 3/4 3-1 3/4 3-6 3/4 3-9 3/4 3-10 3/4 3-21 3/4 3-22 3/4 3-27 3/4 3-33
LIST OF TABLES 1.2 SURVEILLANCEFREQUENCY NOTATION.
OPERATIONAL CONDITIONS 1-9 1-10 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2-4 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.~.~........
~ ~ ~...... 3/4 3-2 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCEREQUIREMENTS 3.3.2-1 ISOLATION ACTUATIONINSTRUMENTATION.
3.3.2-2 ISOLATION ACTUATIONINSTRUMENTATIONSETPOINTS.~.........
4.3.2.1-1 ISOLATION ACTUATIONINSTRUMENTATIONSURVEILLANCE 3/4 3-7
. 3/4 3-11
.. 3/4 3-17 3.3.3-1 REQUIREMENTS EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.
3/4 3-23
. 3/4 3-28 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSETPOINTS 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSURVEILLANCEREQUIREMENTS...
3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.
3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATIONSETPOINTS 3/4 3-31
... 3/4 3-34 3/4 3-37 3/4 3-38 SUSQUEHANNA - UNIT 1 XXII Amendment No.
9g, 148
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LIMITINGCONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown
.in Table 3.3.1-1 shall be OPERABLE.
As shown in Table 3.3.1-1.
SGIIQH:
a.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system:
1.
If placing the inoperable channel(s) in the tripped condition would cause a
scram, the inoperable channel(s) shall be restored to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION required by Table 3.3.1-1 for the affected Functional Unit shall be taken; or 2.
If placing the inoperable channel(s) in the tripped condition would not cause a
- scram, place the inoperable channel(s) and/or that trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement for both trip systems, place at least one trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.1-1.
The provisions of Specification 3.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs or the Neutron Flux - Upscale, Setdown function of the APRMs.
SURVEILLANCEREQUIREMENTS 4.3.F 1 4.3.1.2 4.3.1.3 4.3.1.4 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONALTEST and CHANNEL CALIBRATIONoperations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.
LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shall bg demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.
The provisions of Specification 4.0A are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs or the Neutron Flux-Upscale, Setdown function of the APRMs.
If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause a scram to occur.
~ 0 The neutron detectors are exempt from response time testing.
SUSQUEHANNA - UNIT 1 3/4 3-1 Amendment No. 11)(, 148
SUSQUEHANNA - UNIT 1 3/4 3-6 Amendment No.
41, 148
I LIMITINGCONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2.
As shown in Table 3.3.2-1.
hQIM:
a.
With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel(s) and/or that trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The provisions of Specification 3.0.4 are not applicable.
c.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.2-1
~
An inoperable. channel need not be pIaced in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.
In addition, for the HPCI system and RCIC system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, for the HPCI and RCIC systems, the inoperable channel shall be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the ACTION required by Table 3.3.2-1 for that trip Function shall be taken.
~ ~
If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
SUSQUEHANNA - UNIT 1 3/4 3-9 Amendment No. 29, 148
SURVEILLANCEREQUIREMENTS I
4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONALTEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.2.3 The ISOLATION SYSTEM
RESPONSE
TIME of each isolation trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific isolation trip system.
Neutron detectors are exempt from response time testing.
SUSQUEHANNA - UNIT 1 3/4 3-10 Amendment No.
148
TABLE 3.3.2-:3 ISOL'ATION,'SYSTEM:IMSTRUIYIENTATlON:RESPONSE:TIME..., ':;.':"':;:: ',:
DELETED SUSQUEHANNA - UNIT 1 3/4 3-21 Amendment No. Pal i48
TABLE3.3.2-3 (Continued),"
ISOLATION-SYSTEM.INSTRUMENTATION'RESPONSE TIME SUSQUEHANNA - UNIT 1 3/4 3-22 Amendment No. 86, 121
> 148
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LIMITINGCONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.
As shown in Table 3.3.3-1
~
hGXIQH:
a.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
SURVEILLANCEREQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1
~
4.3.3.2 LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
SUSQUEHANNA - UNIT 1 3/4 3-27 Amendment No.
TABLE 3.3';3-3 EMERGENCY:CORE.,COOLING SYSTEM RESPONSE-TIIVIES DELETED SUSQUEHANNA - UNIT 1 3/4 3-33 Amendment No. j.'24, I 48
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
~CK 5 55.
5 -3 SUS UEHANNA STEAM L
C RIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated April 10,
- 1995, 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 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:
(i) 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
118 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
. Stolz, Dir tor oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 11, 1995
TTACHMENT TO LICENSE AM NDMENT NO, 118 FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE XX1V 3/4 3-1 3/4 3-6 3/4 3-9 3/4 3-10 3/4 3-21 3/4 3-22 3/4 3-27 3/4 3-33 INSERT XxiV 3/4 3-1 3/4 3-6 3/4 3-9 3/4 3-10 3/4 3-21 3/4 3-22 3/4 3-27 3/4 3-33
'h II
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~ i LIST OF TABLES 1.2 SURVEILLANCEFREQUENCY NOTATION.
OPERATIONAL CONDITIONS 1-9 1-10 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2-4 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION~............~....... 3/4 3-2
~ 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCEREQUIREMENTS 3.3.2-1 ISOLATIONACTUATION INSTRUMENTATION.
. 3/4 3-7
... 3/4 3-11 3.3.2-2 ISOLATION ACTUATIONINSTRUMENTATIONSETPOINTS.. ~ ~ ~...~....... 3/4 3-17 4.3.2.1-1 ISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCE 3.3.3-1 REQUIREMENTS EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.
3/4 3-23
..... ~....... 3/4 3-28 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSETPOINTS 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSURVEILLANCEREQUIREMENTS...
3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.
3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATIONSETPOINTS 4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATIONSURVEILLANCEREQUIREMENTS........
3.3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 3/4 3-31
... 3/4 3-34
... 3/4 3-37 3/4 3-38
... 3/4 3-39 3/4 3-42 3.3A.2-2 3.3.4.2-3 END-OF-CYCLE RECIRCULATION PUMP TRIP SETPOINTS.....
END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME ~ ~
....... 3/4 3-43
~.. 3/4 3-44 SUSQUEHANNA - UNIT 2 XXIV Amendment No. 91, 118
LIMITINGCONDITION FOR OPERATION 3.3.1 As a
minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE.
1 As shown in Table 3.3.1-1.
a.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system:
1.
If placing the inoperable channel(s) in the tripped condition would cause a
scram, the inoperable channel(s) shall be restored to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION required by Table 3.3.1-1 for the affected Functional Unit shall be taken; or 2.
If placing the inoperable channel(s) in the tripped condition would not cause a
- scram, place the inoperable channel(s) and/or that trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement for both trip systems, place at least one trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.1-1.
The provisions of Specification 3.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs or the Neutron Flux - Upscale, Setdown function of the APRMs.
SURVEILLANCE REQUIREMENTS 4.3.1.1 4.3.1.2 4.3.1.3 4.3.1.4 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONALTEST and CHANNEL CALIBRATIONoperations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.
LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.
The provisions of Specification 4.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs or the Neutron Flux-Upscale, Setdown function of the APRMs.
1 If more channels. are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause a scram to occur.
~t Neutron detectors are exempt from response time testing.
SUSQUEHANNA - UNIT 2 3/4 3-1 Amendment No. 84, 118
TABLE3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE:,TIMES SUSQUEHANNA - UNIT 2 3/4 3-6 Amendment No. 118
LIIVIITINGCONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2.
As shown in Table 3.3.2-1.
AGIIQH a.
With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel(s) and/or that trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The provisions of Specification 3.0.4 are not applicable.
c.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.2-1.
An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. Tn these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the, ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.
In addition, for the HPCI system and RCIC system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one inoperable channel need not be pieced in the tripped condition where this would cause the Trip Function to occur.
In these
- cases, for the HPCI and RCIC systems, the inoperable channel shall be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the ACTION required by Table 3.3.2-1 for that trip Function shall be taken.
If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
SUSQUEHANNA - UNIT 2 3/4 3-9 Amendment No. >18
SURVEILLANCEREQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONALTEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific isolation trip system.
Neutron detectors are exempt from response time testing.
SUSQUEHANNA - UNIT 2 3/4 3-10 Amendment No. 118
TABLE 3.3.2-3 ISOLATION'SYSTEM:INSTRUMENTATIONRESPONSE'TIIVIE:
DELETED SUSQUEHANNA - UNIT 2 3/4 3-21 Amendment No.g g, g ] 8
TABLE3,3.2-3.{Contintted):.
ISOLATIONSYSTEM INSTRUMENTATION:RESPONSE TllVIE DELET:ED SUSQUEHANNA - UNIT 2 3/4 3-22 Amendment No.
96, 118
LIMITINGCONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.
As shown in Table 3.3.3-1.
a.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
SURVEILLANCEREQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONALTESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
SUSQUEHANNA - UNIT 2 3/4 3-27 Amendment No. 118
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TABL'E"3;3.3-3
'MERGENCY CORE'COOLING:SYSTEM RESPONSE TIMES' SUSQUEHANNA - UNIT 2 3/4 3-33 Amendment No.
94
> 118