Proposed Tech Specs Consisting of Changes to TS 3/4.3.2, Containment & Rv Isolation Control Sys, to Provide Reasonable Period of Time to Detect & Correct Inoperabilities of Differential Temp Isolation InstrumentsML20126B612 |
Person / Time |
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Site: |
Clinton ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
12/15/1992 |
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From: |
ILLINOIS POWER CO. |
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To: |
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Shared Package |
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ML20126B588 |
List: |
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References |
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NUDOCS 9212220150 |
Download: ML20126B612 (8) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources ML20078Q2931995-02-14014 February 1995 Proposed Tech Specs 3.8.2, AC Sources-Shutdown, 3.8.5, DC Sources-Shutdown & 3.8.8, Inverters-Shutdown ML20078N2701995-02-10010 February 1995 Proposed TS 3.3.2.1, Control Rod Block Instrumentation ML20078E9701995-01-27027 January 1995 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements U-602372, Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 19921994-11-18018 November 1994 Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 1992 ML20076G2721994-10-14014 October 1994 Proposed Tech Specs,Allowing Drywell Bypass Leakage Test to Be Performed at five-yr Interval ML20072E6701994-08-12012 August 1994 Proposed Tech Specs Eliminating Requirement to Perform Manual Testing of solid-state Logic Independently from self-test Sys ML20072E6191994-08-12012 August 1994 Proposed Tech Specs Allowing Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years ML20072C1251994-08-0505 August 1994 Proposed Tech Specs Re Requirement for Accelerated Testing of Div 1 DG ML20069Q3851994-06-27027 June 1994 Proposed Tech Specs 3/4.4.3.1, Reactor Coolant Sys Leakage- Leakage Detection Sys ML20069N3201994-06-16016 June 1994 Proposed Tech Specs Adding -89 After ASTM D3803 in Testing Requirements Specified for SGTS & MCR Filter Sys Charcoal & Changing Test Temp for Testing SGTS Charcoal from 80 C to 30 C ML20069K8191994-06-13013 June 1994 Proposed Tech Specs to Allow 36-inch Isolation Valve Leak Measurement Be Performed at Least Once Per 18 Months, Providing Valves Remain Closed During Period ML20070N6951994-04-26026 April 1994 Proposed Tech Specs Adopting Changes Recommended in NRC Re NUREG-1434 1999-01-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999 1999 Business Plan ML20206F2231999-04-27027 April 1999 NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station ML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20206E6281998-12-31031 December 1998 Rev 17 to ODCM for Clinton Power Station ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20236Q4661998-07-17017 July 1998 Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4651998-07-17017 July 1998 Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4571998-07-17017 July 1998 Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20203D5651998-02-19019 February 1998 Plan for Excellence ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition ML20149H8991997-06-30030 June 1997 CPS Long Term Improvement Plan U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20137A1101996-08-14014 August 1996 Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan ML20137A1021996-07-10010 July 1996 Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20117E3001995-11-0606 November 1995 Rev 18 to App V Pump & Valve Testing Program Plan ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20087J5691995-05-17017 May 1995 Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources 1999-07-06
[Table view] |
Text
_ - _ - _ _ _ _ _ _ -_ .
Attachment 3 to U-602070 LS-92-002 Page I of g INSTRUMEFTATION 3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING COPDITION FOR OPERATION 3.3.2 The containment and ret etor vessel isolation control system (CRVICS) channels shown in Table 3.3,2-1 shall be OPERABLE
- with their tr'ip setpoints set 3
consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
(
A_. PPLICABILITY: As shown in Table 3.3.2-1.
ACTI0ti:
a.
With a CRVICS channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.2-2, de setpoint adjusted consistent with the Trip Setpoint value, .'
- b. For CRVICS Main Steam Line Isolation Trip Functions:
1.
With one of the four channels required for any Trip Function inopera-ble, operation may continue provided theThe inoperable provisionschannel of Speci-is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
fication 3.0.4 are not applicable.
2.
With two of the four c .nnels required for any Trip Function inopera-ble, place one channel in the tripped condition within one hour provided no tripped channel for that Trip Function already exists.
The provisions of Specification 3.0.4 are not applicable. -
or l 3.
With three d 9 e four channels required for any Trip Function inoperable M e the ACTION required by Table 3.3.2-1.
- c. For other CRVICS Isolation Trip Functions:
1.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tr,ip System requirement for one trip system, place the inoperable channel (s) and/orofthat The provisions trip system Specification inare 3.0.4 the t, ripped condition ** within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
not applicable, h
n er o 58' go do
- For CRVICS Main Steam Line Isolation Trip Function, a cha at least two OPERABLE channels are monitoring that parameter.
og
- For other CRVICS Isolation Trip Function, a channel may be placed in an in-
.o operable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance provided the
@ requirements of Table 3.3.2-1 are fulfi.11ed.
g **An inoperable channel need not be placed gg .
In thesein the tripped cases, condition where this the inoperable would cause the Trip Function to occur.
d o. n.
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 AC required by Table 3.3.2-1 for that Trip Function shall be taken.
3/4 3-11 CLINT3H - UNIT 1 l
--- _ ____ ~
r
Attachment 3 Mo chcm es , ~Jh g n g g to U-602070 Y
A f , t h.f A -
f N Np U Pa e of 8
'1 INSTRUMENTATION CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM L]MITING CONDITION FOR OPERATION (Continued) 3.3.2 ACTION (Continued)_:
2.
With the number of OPERABLE channels less than required by the Min OPERABLE Channels per Trip System requirem and take the ACTION required by Table 3.3.2-1.
SURVEILLANCE REQUIREMENTS Each CRVICS channel shall be demonstrated OPERABLE tions by the perform 4.3.2.1 of the CHANNEL CHECK, CHANNEL FUNCTIONAL 4.3.2.2 18 months.
LOGIC SYSTEM FUNCTIONAL TESTS shall SELF be perfor the chanrel coincident logic shall be manually tested independent of the'Eac TEST SYSTEM during each refueling outage.
divisions of the CRVICS tri.p system logic rshall be alternately t and manuall tested independent of the SELF TEST SYSTEN during eve'y' othef iefueling o All manual testing shall be completed such that all tri_p functions are teste at least once every four fuel cycles.**
'4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 18 months.
3.3.2-3 shall be demonstrated to be withinl its limit at l once per 36 months, and one channel per trip function of redundant channels in a specific CRVICS trip function.
i ld "The trip system need not be placed in the tripped condition if th s. wou cause the Trip Function to occur. . When.a trip -system can be'placed i in the tripped condition without causing the Trip Function to occur, place the tr p system systems have th2 with the most inoperable. channels in the tripped in the tripped condition.
- Manual testing for the purpose of ' satisfying Specification 4.3.2.2 f ling-is not required until af ter shutdown during the first- regularly scheduled re ue outage.
3/4 3-12 CLINTON - UNIT 1
(~C 3 f 8 ?)
5o/
% .)
p TABLE 3.3.2-1 rt, p CRVICS INSTl!UMENTATION
= p
.$gi
' HINIMUM OPERABLE APPLICABLE l .f g ISOLATION CHANNELS PER TRIP OPERATIONAL j q TRIP FUNCTION SIGNAL.tt SYSTEM CONDITION ACTION .-
H 1. PRIMARY AND SECONDARY CONTAINMENT ISOLATION .>
- a. Reactor Vessel Water Level-Low Low, B(b)(f) 2(a) 1, 2, 3 20 [
Level 2 # 25 ,
- b. Reactor Vessel ilater Level-Low 2 58) 1, 2, 3 29 B
' Low, Level 2 (ECCS Div. I and II)
- c. Reactor Vessel Water Level-Low, L w , B 2(a)(m) 1,2,3 29 bN ep '
w Level 2 (HPCS-NSPS Div. III ano IV) p
- d. D.rywell Pressure - High L(b)(f) 2 1,2,3 20 g e. Drywell Pressure - High L 2 1,2,3 29 (ECCS'Div. I and II) 2(a)(n)
- f. Drywell Pressure - High .(HPCS-NSPS L 1, 2, 3 29 Div. III and IV)
- g. Containment Building fuel Transfer Z(b)(f) 2(a) ## 25 Pool Ventilation Plenum Radiation - High
- h. Containnent Building Exhaust Radiation - High
- 1) Outi,oard (Div. I) Valve Isolation M(b)(f) 2(")( ) 1, 2, 3 29
- 25 g 2) Inboard (Div. II) Valve Isolation M ID)(I) 2(a)(o) 1, 2, 3 29
- 25
-E i. Containment Building Continuous 5(b)(f) 2(a) .
2, 3 29 s
Containment Purge (CCP) Exhaust # 25 Radiation - High J. Reactor Vessel Water Level-Low U 2(k) 1, 2, 3 29 2CER
$ Low Low, Level 1 # 25 % i c: ;
~
- k. Containment Pressure-High P 1(k)(1) 1, 2, 3 29 hh
- 25 Syg
= s"u
l 5-Qo p TABLE 3.3.2-1 (Continued) he n}
I k CRVICS If4STRUMENTATION
'NJ l E c MINIMUM OPERABLE APPLICAbl.E 5 ISOLATION SIGNAL tt CHANNELS PER TRIP SYSTEM DeZRATIONAL CONDITION ACT10tl 6 'd 1 TRIP FUNCTION _
[ 2(a) 1, 2, 3 23 < -k j
- l. Main Steam Line Radiation - liigh C ~
Fuel Building Exhaust (b)(f)(j) 2(*) 1, 2. 3 25 9 )
i Radiation a liigh # 25 gQ~N R(b)(f) 1 1,2,3 26 3 )
- n. M.inual Initiat an # 25
)
ISOLATION APPLICABLE APPLICABLE OPERATIONAL nff y 2. MIN STEAM LINE ISOL/JION t SIGNAL TABLE NOTES CONDITI0fl5 ACT10t. g' 5
w a. Reactor Vessel Water Level-Lcv HA 1, 2, 3 20 A low Low, Level 1 U
- b. Main Steam Line Radiation - liigh C H
4 NA 1,2,3 1
23 23
([-
- c. Main Steam Line Pressure - Low
- d. Main-steam Line Flow - liigh D NA 1,2,3 23
- e. Condenser Vacuum - Low J NA 1, 2**, 38^ 23
- f. Main Stean Line Tunnel Temp.
- High i. NA 1,2,3 23
- g. Main Steam Line TunneI a Temp.
- liigh F HA 1,2,3 23
- h. Main Steam Line Turb be 61dg.
Temp. - High G p 1,2,3 23 l
- i. Manual Initiation R NA 1,2,3 22
, p B
e
- e - :n-i c eea9 k
,o 8 !!
~fj, T C
. i i
' TABLE 3.3.2-1 (Continued) . >
~06 ~@-
l n
r-CRVICS INSTRUMENTATION OD -
h APPLICABLE b5 !
. c,
- ISOLATION CHANNELS PER TRIP SYSTEM CONDITION ACTIOk % ,
SIGNAL tt
~
. _E . TRIP FUNCTION p.O .
- 3. REACTOR WATfR CLEANUP SYSTEM _ ISOLATION g) 1,2,3 27 W j
"[ a. A Flcw - High 1 1(k)-
1 1,2,3 27 ~~
X _>
- b. A Flow Timer --)
- c. Equipment' Area Temp. - High N 1/ room g) 1, 2, 3 27 p r
- 1. : Pump Rooms - A, 8. C .
^ 'l-
- 2. Heat Exchanger Rooms - East, 1/ room (k) 1, 2, 3 27-N i West ,
27 i
- d. . Equipment Area A Temp. - High- 1/ room (k) 1, 2, 3 2
. 1.' Pump Rooms - A, B, C 27 GO
'2. Hest Exchanger Rooms - East, 1/ room (k) 1, 2, 3 ,
2
' West Reactor Vessel Water -1,2,3 29 ,
w ' e.
Level.- Low Low, Level 2- B 2(k) 25 d
- 1 M w, .
y ,. 2, 3 27
.O f. Main Steam Line Tunnel. 1(k)
F. I(k) 1, 2, 5* 27 ATemp. -'Highg X 1
- h. 'SLCS Initiation ,g)g) 1,2,3 26 R 1
- i. Manual Initiation # 25 i
- 4. . REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION b) 1, 2, 3 27
'High V l RCIC' Steam Line Flow
[3 a.
.RCIC Steam Line Flow - High' 27' i
1, 2, 3 F
.{
2
.b.
Timer X 1(k) ,
i
- c. RCIC Steam Supply 1,.2, 3 27 E V(h)- 1(k)
Pressure - Low En
- d. ;RCIC Turbine Exhaust 1, 2, 3 27 *4?R',
V 2(k) "68[
Diaphragm Pressure - High 2, 8 a~ a,,
f W.
j e
-Q OZ i TABLE 3.3.2-1 (Continued) @O 6
j 1
E CRVICS INSTRUMENTATION .
-f
$ '%%) ,.
~
' \
MINIMUM OPERABLE APPLICABLE OPERATIONAL u E ISOLATION CHANNELS PER TRIP SIGNAL tt SYSTEM CONDITION ACTION l Q TRIP FUNCTION -
s s'
- 4. REACTOR CORE ISOLATION. COOLING SYSTEM ISOLATION (Continued) '
- e. RCIC Equipment Room Ambient Temp. - High V 1(k) 1, 2, 3 27 .'3Jf
- f. RCIC Equipment Room A Temp. - H'gh V 1(k) 1,2,3 27
- g. Main Steam Line Tunnel f g Ambient. Temp. - High E 1(k) 1, 2, 3 27 I h 3
y h. Main Steam Line Tunnel a Temp. - High 1(k) 1,2,3 27 g
F
- i. Main Steam Line Tunnel Temperature Timer X 1(k) 1, 2, 3 27
- j. Drywell Pressure - High L(h) 7(k) 1, 2, 3 27
- k. Manual Initiation R 1(I) 1,2,3 26
- 1. RHR/RCIC Steam Line Flow - High V 1(k) 1,.2, 3 27 k m. RHR Heat Exchanger A, B. T 1/ room (k) '
1, 2, 3 28
{ Ambient Temperature - High ;
k n. RHR Heat 4 anger A, 8 S 1/ room (k) 1, 2, 3 28 z A'Teq High
?
xI G, " R ,
N
,883 m 8"
o
~C 25-gO TABLE 3.3.2-1 (Continued)
.p b C_ )
CRVICS INSTRUMENTATION
$ D g foPLICABLE 5
. MINIMUM OPERABLE ,
OPERATIONAL e ISOLATION' CHANNELS PER TRIP ACTION z CONDITION SIGNAL tt SYSTEM
. TRIP FUNCTION
- );
- 5. RHR SYSTEM ISOLATION >J_1 --
28
- a. RHR Heat Exchanger A B Ambient Temperature --High T 1/ room (k) 1, 2, 3
[lA 3
- b. RHR. Heat Exchanger'A, B 1/ room (k) 1,.2, 3 28 Q S
ATemp. - High Q i
- c. Reactor Vessel Water 2(a) 1,2,3 28 (9 p i w LLevel - Low, Level 3 A'
} f-1, 2, 3 28 Y d. Reactor Vessel Water Level - U 2(k)
U Low Low Low, Level.1 1, 2, 3 28
- e. Reactor Vessel (RHR Cut-in .5 2(a)
, Permissive)' Pressure - High
~f. Drywell Pressure - High 28 1,2,3
- 1) 'RHR Test Lines .
L L
2f3 2
~ 1, 2, 3 28
- 2) . Fuel-' Pool Cooling..
1 1,.2, 3 26 R.
- g. Manual Initiation i
" k us o n
= % e n C @ Ck PO a n "aai P,8aa-
= 0 ",
. Attachment 3 to U-602070 LS-92-002 Page 8 of 8 TABLE 3.3.2-1 (Continued)
CRVICS INSTRUMENTATION l l
ACTION ACTION 20 - Be in at least HOT SHUT 00W within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00W within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 21 -
Deleted.
ACTION 22 - With one channel in either trip system inoperable restore the manu i initiation function to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOW within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 23 -
Be in at least STARTU with the associated isolation valves closed hin 6 hou r be in at least fl0T SHUTOOWN within 12 hou nd in COLD SHUT 00W within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
]
ACTION 24 - Be in ct least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 25 - CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling irradiated fuel in the primary or secondary containment may continue provided that SECONDARY CONTAINMENT INTEGRITY is established with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 26 -
Restore the manual initiation function to OPERABLE statun i within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the'next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHtff00W within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 27 - Close the affected system isolation valves within 1 ho nd l declare the affected system inoperable.
ACTION 28 - Lock the affected system icolation valves closed within 1 ho l and declare the affected system inoperable.
ACTION 29 - Operations may continue provided that the affected CRVICS isola-tion valve (s) are closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and, as appropriate, declare the affected system or component inoperable and follow any ACTIONS appropriate to Specifications of the affected system. Otherwise, be in HOT SHUT 00W within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
-me-qnd in COLD SHUT 00W within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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