RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control: Difference between revisions

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{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-17-145 10 CFR 50.90 November 15, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-17-145 10 CFR 50.90 November 15, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461  


==Subject:==
==Subject:==
Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control"
Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control"  


==References:==
==References:==
(1)   Letter from P. R. Simpson (Exelon Generation Company, LLC (EGC)) to NRC, "Application to Revise Technical Specifications to Adopt TSTF-542,
(1)
                        'Reactor Pressure Vessel Water Inventory Control,'" dated April 27, 2017 (2)   Email from J. Rankin (NRC) to M. A. Mathews (EGC), "Clinton Power Station - Request for Additional Information Regarding License Amendment Request Related to Reactor Pressure Vessel Water Inventory Control (CAC No. MF9666)," dated October 3, 2017 In Reference 1, Exelon Generation Company, LLC (EGC) submitted a request for an amendment to the Technical Specifications (TS) for Clinton Power Station (CPS), Unit 1.
Letter from P. R. Simpson (Exelon Generation Company, LLC (EGC)) to NRC, "Application to Revise Technical Specifications to Adopt TSTF-542,  
'Reactor Pressure Vessel Water Inventory Control,'" dated April 27, 2017 (2)
Email from J. Rankin (NRC) to M. A. Mathews (EGC), "Clinton Power Station - Request for Additional Information Regarding License Amendment Request Related to Reactor Pressure Vessel Water Inventory Control (CAC No. MF9666)," dated October 3, 2017 In Reference 1, Exelon Generation Company, LLC (EGC) submitted a request for an amendment to the Technical Specifications (TS) for Clinton Power Station (CPS), Unit 1.
In Reference 2, the NRC determined that additional information was required to complete its evaluation of the Reference 1 request. The requested information, along with one additional variation from TSTF-542 related to the manual operation of a required emergency core cooling subsystem is provided in the attachments to this letter.
In Reference 2, the NRC determined that additional information was required to complete its evaluation of the Reference 1 request. The requested information, along with one additional variation from TSTF-542 related to the manual operation of a required emergency core cooling subsystem is provided in the attachments to this letter.
Additionally, on May 26, 2017, the NRC issued Operating License Amendment No. 212 for CPS, Unit 1. This amendment allows for the adoption of TSTF-545, "TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing." Attachment 2 to this letter provides revised markups of the CPS, Unit 1 TS to address issues identified in Reference 2, the adoption of TSTF-545, and the additional variation discussed above. These markups supersede those provided in Reference 1, Attachment 2 in their entirety. Attachment 3 provides the accompanying revised TS pages associated with the modifications shown in Attachment 2 as discussed above. Likewise, these pages supersede those provided in Reference 1, Attachment 3. Attachment 4 provides a markup of the TS Bases pages affected by the additional variation discussed above for information only.
Additionally, on May 26, 2017, the NRC issued Operating License Amendment No. 212 for CPS, Unit 1. This amendment allows for the adoption of TSTF-545, "TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing." Attachment 2 to this letter provides revised markups of the CPS, Unit 1 TS to address issues identified in Reference 2, the adoption of TSTF-545, and the additional variation discussed above. These markups supersede those provided in Reference 1, Attachment 2 in their entirety. Attachment 3 provides the accompanying revised TS pages associated with the modifications shown in Attachment 2 as discussed above. Likewise, these pages supersede those provided in Reference 1, Attachment 3. Attachment 4 provides a markup of the TS Bases pages affected by the additional variation discussed above for information only.  


November 15, 2017 U.S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC ln Reference 1.
November 15, 2017 U.S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC ln Reference 1.
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Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15th day of November 2017.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15th day of November 2017.
RfmR Patrick R. Simpson Manager- Licensing Exelon Generation Company, LLC Attachments:       1. Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1
RfmR Patrick R. Simpson Manager-Licensing Exelon Generation Company, LLC Attachments:
: 2. Proposed Technical Specifications Changes (Mark-Up)
: 1.
: 3. Revised Technical Specifications Pages
Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1
: 4. Technical Specifications Bases Pages Affected by the Additional Variation (Mark-Up}
: 2.
cc:     NRG Regional Administrator, Region Ill NRC Senior Resident Inspector- Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
Proposed Technical Specifications Changes (Mark-Up)
: 3.
Revised Technical Specifications Pages
: 4.
Technical Specifications Bases Pages Affected by the Additional Variation (Mark-Up}
cc:
NRG Regional Administrator, Region Ill NRC Senior Resident Inspector-Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety  


Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 1 -
Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 1 -
Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1
Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1


SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT 1 LICENSE AMENDMENT REQUEST RELATED TO REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL DOCKET NO. 50-461 By application dated May 1, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17121A517), Exelon Generation Company, LLC (the licensee),
SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 1 of 4 REQUEST FOR ADDITIONAL INFORMATION EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT 1 LICENSE AMENDMENT REQUEST RELATED TO REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL DOCKET NO. 50-461 By application dated May 1, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17121A517), Exelon Generation Company, LLC (the licensee),
requested a change to the technical specifications (TSs) for Clinton Power Station, Unit 1 (CPS). The proposed change adopts technical specifications task force (TSTF) traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2 (ADAMS Accession No. ML16074A448). Specifically, the proposed changes would replace the existing requirements in the TSs related to operation with a potential for draining the reactor vessels (OPDRVs) with revised TSs providing an alternative for reactor pressure vessel water inventory control (RPV WIC). These alternative requirements would protect Safety Limit 2.1.1.3, which requires RPV water level to be greater than the top of active fuel.
requested a change to the technical specifications (TSs) for Clinton Power Station, Unit 1 (CPS). The proposed change adopts technical specifications task force (TSTF) traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2 (ADAMS Accession No. ML16074A448). Specifically, the proposed changes would replace the existing requirements in the TSs related to operation with a potential for draining the reactor vessels (OPDRVs) with revised TSs providing an alternative for reactor pressure vessel water inventory control (RPV WIC). These alternative requirements would protect Safety Limit 2.1.1.3, which requires RPV water level to be greater than the top of active fuel.
TSTF-542, Revision 2, was approved by the U.S. Nuclear Regulatory Commission (NRC) on December 20, 2016 (ADAMS Accession No. ML16343B008).
TSTF-542, Revision 2, was approved by the U.S. Nuclear Regulatory Commission (NRC) on December 20, 2016 (ADAMS Accession No. ML16343B008).
Based on its review of the amendment request, the NRC staff has determined that additional information is required to complete the review.
Based on its review of the amendment request, the NRC staff has determined that additional information is required to complete the review.  


===RAI 1===
===RAI 1===
The staff has identified an apparent discrepancy in Attachment 2, page 3.5-11 of the license amendment request (LAR). Specifically, the current TSs (i.e., current TS surveillance requirements 3.5.2.5 and 3.5.2.6) contain text not shown in the proposed markup as being deleted.
The staff has identified an apparent discrepancy in Attachment 2, page 3.5-11 of the license amendment request (LAR). Specifically, the current TSs (i.e., current TS surveillance requirements 3.5.2.5 and 3.5.2.6) contain text not shown in the proposed markup as being deleted.
For clarity, please correct the proposed TS markup, as appropriate Exelon Generation Company, LLC (EGC) Response The markups for SR 3.5.2.5 and SR 3.5.2.6 are incorporated in the revised TS markups included in Attachment 2 on Page 3.5-10.
For clarity, please correct the proposed TS markup, as appropriate Exelon Generation Company, LLC (EGC) Response The markups for SR 3.5.2.5 and SR 3.5.2.6 are incorporated in the revised TS markups included in Attachment 2 on Page 3.5-10.  
Page 1 of 4


SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1
SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 2 of 4


===RAI 2===
===RAI 2===
TSTF-542, Revision 2 changes the title of TS 3.5.2 from "ECCS - Shutdown" to "RPV Water Inventory Control." Current TS 3.8.2, "AC Sources - Shutdown," TS 3.8.5, "DC Sources -
TSTF-542, Revision 2 changes the title of TS 3.5.2 from "ECCS - Shutdown" to "RPV Water Inventory Control." Current TS 3.8.2, "AC Sources - Shutdown," TS 3.8.5, "DC Sources -
Shutdown," and TS 3.8.8, "Inverters - Shutdown," reference TS 3.5.2, "ECCS- Shutdown."
Shutdown," and TS 3.8.8, "Inverters - Shutdown," reference TS 3.5.2, "ECCS-Shutdown."
There was not any revised TS pages submitted in the LAR to reflect the changes to these sections.
There was not any revised TS pages submitted in the LAR to reflect the changes to these sections.
Please provide revised and markup TS pages for these sections, as appropriate.
Please provide revised and markup TS pages for these sections, as appropriate.
EGC Response The requested changes are incorporated in the revised markups included in Attachment 2 on Pages 3.8-16, 3.8-27, and 3.8-36.
EGC Response The requested changes are incorporated in the revised markups included in Attachment 2 on Pages 3.8-16, 3.8-27, and 3.8-36.
RAl 3 , pages 3.3-54 through 3.3-59 of the LAR provides a markup of Table 3.3.6.1-1, "Primary Containment and Drywell Isolation Instrumentation." Due to the deletion of Footnote (c), which states, "During operations with a potential for draining the reactor vessel," the following instrumentation were affected.
RAl 3  
, pages 3.3-54 through 3.3-59 of the LAR provides a markup of Table 3.3.6.1-1, "Primary Containment and Drywell Isolation Instrumentation." Due to the deletion of Footnote (c), which states, "During operations with a potential for draining the reactor vessel," the following instrumentation were affected.
Function 2 (Primary Containment and drywell isolation), Item a, "Reactor Vessel Water Level Low Low, Level 2" Function 2, Item g, "Containment Building Fuel Transfer Pool Ventilation Plenum Radiation High" Function 2, Item h, "Containment Building Exhaust Radiation High" Function 2, Item i, "Containment Building Continuous Containment Purge (CCP) Exhaust Radiation High" Function 2, Item j, "Reactor Vessel Water Level Low Low Low, Level 1" Function 2, Item l, "Manual Initiation" Function 4 (reactor water cleanup system isolation), Item f, "Reactor Vessel Level Low Low, Level 2" Function 4, Item h, "Manual Initiation" Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation" in TSTF-542, Revision 2 modifies Function 2.g, "Containment and Drywell Ventilation Exhaust Radiation High," in relation to the removal of Footnote (b) which states, "or operations with a potential for draining the reactor vessel."
Function 2 (Primary Containment and drywell isolation), Item a, "Reactor Vessel Water Level Low Low, Level 2" Function 2, Item g, "Containment Building Fuel Transfer Pool Ventilation Plenum Radiation High" Function 2, Item h, "Containment Building Exhaust Radiation High" Function 2, Item i, "Containment Building Continuous Containment Purge (CCP) Exhaust Radiation High" Function 2, Item j, "Reactor Vessel Water Level Low Low Low, Level 1" Function 2, Item l, "Manual Initiation" Function 4 (reactor water cleanup system isolation), Item f, "Reactor Vessel Level Low Low, Level 2" Function 4, Item h, "Manual Initiation" Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation" in TSTF-542, Revision 2 modifies Function 2.g, "Containment and Drywell Ventilation Exhaust Radiation High," in relation to the removal of Footnote (b) which states, "or operations with a potential for draining the reactor vessel."
Compared to the TSTF-542, Revision 2, CPS proposed to delete additional instrumentation (related to the Applicability during Modes 4 and 5 or OPDRVs) from its TSs. Please provide a technical variation to describe the deviations between the proposed CPS TSs and TSTF 542, Revision 2.
Compared to the TSTF-542, Revision 2, CPS proposed to delete additional instrumentation (related to the Applicability during Modes 4 and 5 or OPDRVs) from its TSs. Please provide a technical variation to describe the deviations between the proposed CPS TSs and TSTF 542, Revision 2.  
Page 2 of 4


SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 EGC Response All of these instrument functions serve to isolate Primary Containment penetrations that bypass Secondary Containment; therefore, they function to isolate a portion of the Secondary Containment boundary for Clinton Power Station (CPS), Unit 1. Under the proposed Technical Specification (TS) 3.5.2 "Reactor Pressure Vessel Water Inventory Control," requirements, Secondary Containment must be isolated or capable of being isolated in less than the Drain Time when the Drain Time is less than 36 hours, but automatic Secondary Containment isolation is not required. A draining event is a slow evolution when compared to a design basis loss of coolant accident that is assumed to occur at full power, and thus there is adequate time to take manual actions (i.e., hours versus minutes). The proposed TS 3.5.2, Action E, prohibits plant conditions that could result in Drain Times less than one hour. Therefore, there is sufficient time for the licensed operators to take manual action to stop the draining event, or to establish the Secondary Containment boundary and to isolate the Secondary Containment penetration flow paths before Secondary Containment isolation would be required.
SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 3 of 4 EGC Response All of these instrument functions serve to isolate Primary Containment penetrations that bypass Secondary Containment; therefore, they function to isolate a portion of the Secondary Containment boundary for Clinton Power Station (CPS), Unit 1. Under the proposed Technical Specification (TS) 3.5.2 "Reactor Pressure Vessel Water Inventory Control," requirements, Secondary Containment must be isolated or capable of being isolated in less than the Drain Time when the Drain Time is less than 36 hours, but automatic Secondary Containment isolation is not required. A draining event is a slow evolution when compared to a design basis loss of coolant accident that is assumed to occur at full power, and thus there is adequate time to take manual actions (i.e., hours versus minutes). The proposed TS 3.5.2, Action E, prohibits plant conditions that could result in Drain Times less than one hour. Therefore, there is sufficient time for the licensed operators to take manual action to stop the draining event, or to establish the Secondary Containment boundary and to isolate the Secondary Containment penetration flow paths before Secondary Containment isolation would be required.
Consequently, there is no need for automatic initiation of Secondary Containment isolation to respond to an unexpected draining event. The Required Actions of proposed TS 3.5.2 will require Secondary Containment isolation, or verification that it can be manually isolated, when the Drain Time is less than 8 hours and no draining event has occurred. This provides a greater level of safety. Excluding these functions from Table 3.3.5.2-1 is addressed by the proposed Limiting Condition for Operation (LCO) 3.5.2, "RPV Water Inventory Control." Specifically, by LCO 3.5.2, Required Actions C.1 and D.2 which are: "Verify secondary containment boundary is capable of being established in less than the DRAIN TIME," and "Initiate action to establish secondary containment boundary," respectively. This approach is consistent with Section 3.4.1.3 of the Justification for TSTF-542, Revision 2.
Consequently, there is no need for automatic initiation of Secondary Containment isolation to respond to an unexpected draining event. The Required Actions of proposed TS 3.5.2 will require Secondary Containment isolation, or verification that it can be manually isolated, when the Drain Time is less than 8 hours and no draining event has occurred. This provides a greater level of safety. Excluding these functions from Table 3.3.5.2-1 is addressed by the proposed Limiting Condition for Operation (LCO) 3.5.2, "RPV Water Inventory Control." Specifically, by LCO 3.5.2, Required Actions C.1 and D.2 which are: "Verify secondary containment boundary is capable of being established in less than the DRAIN TIME," and "Initiate action to establish secondary containment boundary," respectively. This approach is consistent with Section 3.4.1.3 of the Justification for TSTF-542, Revision 2.
Additional Proposed Variation for Instrumentation Functions:
Additional Proposed Variation for Instrumentation Functions:
EGC proposes to revise Table 3.3.5.2-1, "RPV Water Inventory Control Instrumentation," to reflect the CPS, Unit 1 design. Specifically, Function 1, "Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS) Subsystems," Function 1.d, "Manual Initiation,"
EGC proposes to revise Table 3.3.5.2-1, "RPV Water Inventory Control Instrumentation," to reflect the CPS, Unit 1 design. Specifically, Function 1, "Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS) Subsystems," Function 1.d, "Manual Initiation,"
Function 2, "LPCI B and LPCI C Subsystems," Function 2.c, "Manual Initiation," and Function 3, High Pressure Core Spray (HPCS) System, Function 3.a, "Reactor Vessel Water Level - High, Level 8," and Function 3.e, "Manual initiation," that appear in the BWR/6 Technical Specifications in TSTF-542 are no longer included in the CPS Technical Specifications as proposed. This corrects an issue in TSTF-542 associated with the BWR/5 and BWR/6 emergency core cooling system (ECCS) instrumentation requirements.
Function 2, "LPCI B and LPCI C Subsystems," Function 2.c, "Manual Initiation," and Function 3, High Pressure Core Spray (HPCS) System, Function 3.a, "Reactor Vessel Water Level - High, Level 8," and Function 3.e, "Manual initiation," that appear in the BWR/6 Technical Specifications in TSTF-542 are no longer included in the CPS Technical Specifications as proposed. This corrects an issue in TSTF-542 associated with the BWR/5 and BWR/6 emergency core cooling system (ECCS) instrumentation requirements.
The purpose of the manual initiation functions is to allow manual actuation of the ECCS subsystems required by TS 3.5.2 to mitigate a draining event. Licensed operators in the Main Control Room have the capability to manually start the LPCI, LPCS, and HPCS pumps and to manually align valves to add water inventory, if needed. This can be accomplished without the "Manual Initiation" functions, and the "Reactor Vessel Water Level-High, Level 8" function associated with HPCS. If the water level is above Level 8, and HPCS is the required ECCS subsystem, the Level 8 function can be intentionally defeated to allow the HPCS injection valve to be opened, if needed to control inventory. All actions can be performed from the Main Page 3 of 4
The purpose of the manual initiation functions is to allow manual actuation of the ECCS subsystems required by TS 3.5.2 to mitigate a draining event. Licensed operators in the Main Control Room have the capability to manually start the LPCI, LPCS, and HPCS pumps and to manually align valves to add water inventory, if needed. This can be accomplished without the "Manual Initiation" functions, and the "Reactor Vessel Water Level-High, Level 8" function associated with HPCS. If the water level is above Level 8, and HPCS is the required ECCS subsystem, the Level 8 function can be intentionally defeated to allow the HPCS injection valve to be opened, if needed to control inventory. All actions can be performed from the Main  


SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Control Room and can be accomplished well within the one-hour minimum drain time limit specified in TS 3.5.2, Condition E.
SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 4 of 4 Control Room and can be accomplished well within the one-hour minimum drain time limit specified in TS 3.5.2, Condition E.
The Reactor Vessel Water Level High, Level 8 signal (i.e., TSTF-542, Table 3.3.5.2-1, Function 3.a) prevents overfilling of the reactor vessel into the main steam lines by closing the HPCS injection valves when the water level is above the Level 8 setpoint. Therefore, if HPCS is the required ECCS subsystem and the water level is above Level 8, using the "Manual Initiation" Function 3.e will not result in inventory injection into the reactor vessel until the water level drops below the Level 8 setpoint. If the Level 8 function is retained in Table 3.3.5.2-1, the function would need to be rendered inoperable in order to inject water when the water level is above the Level 8 setpoint.
The Reactor Vessel Water Level High, Level 8 signal (i.e., TSTF-542, Table 3.3.5.2-1, Function 3.a) prevents overfilling of the reactor vessel into the main steam lines by closing the HPCS injection valves when the water level is above the Level 8 setpoint. Therefore, if HPCS is the required ECCS subsystem and the water level is above Level 8, using the "Manual Initiation" Function 3.e will not result in inventory injection into the reactor vessel until the water level drops below the Level 8 setpoint. If the Level 8 function is retained in Table 3.3.5.2-1, the function would need to be rendered inoperable in order to inject water when the water level is above the Level 8 setpoint.
Consequently, Table 3.3.5.2-1, Functions 1.d, 2.c, 3.a, and 3.e, and TS 3.3.5.2, Condition E and associated Required Actions E.1, and E.2 as described in TSTF-542 are not needed to actuate the LPCI, LPCS, and HPCS subsystem components to mitigate a draining event, and are not included in the proposed Table 3.3.5.2-1 for CPS. The remaining functions and Conditions have been renumbered accordingly.
Consequently, Table 3.3.5.2-1, Functions 1.d, 2.c, 3.a, and 3.e, and TS 3.3.5.2, Condition E and associated Required Actions E.1, and E.2 as described in TSTF-542 are not needed to actuate the LPCI, LPCS, and HPCS subsystem components to mitigate a draining event, and are not included in the proposed Table 3.3.5.2-1 for CPS. The remaining functions and Conditions have been renumbered accordingly.
To address the changes associated with the proposed additional variation discussed above, EGC also proposes that Surveillance Requirement (SR) SR 3.5.2.8 be modified to verify that the CPS, Unit 1 required ECCS injection/spray subsystem can be manually operated from the Main Control Room in accordance with the Surveillance Frequency Control Program as shown in Figure 1 below. This will ensure that the required ECCS injection/spray subsystem is Operable and can be manually aligned to provide RPV inventory makeup, if required to do so, without delay.
To address the changes associated with the proposed additional variation discussed above, EGC also proposes that Surveillance Requirement (SR) SR 3.5.2.8 be modified to verify that the CPS, Unit 1 required ECCS injection/spray subsystem can be manually operated from the Main Control Room in accordance with the Surveillance Frequency Control Program as shown in Figure 1 below. This will ensure that the required ECCS injection/spray subsystem is Operable and can be manually aligned to provide RPV inventory makeup, if required to do so, without delay.
Figure 1: Proposed SR 3.5.2.8 Page 4 of 4
Figure 1: Proposed SR 3.5.2.8  


Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES (MARK-UP)
Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES (MARK-UP)
TOC Page ii                       3.3-48                          3.6-7 TOC Page iii                       3.3-49                          3.6-9 TOC Page iv                       3.3-50                          3.6-14 1.0-1                         3.3-51                          3.6-43 1.0-2                          3.3-52                          3.6-44 1.0-3                          3.3-53                          3.6-47 1.0-4                          3.3-54                          3.6-49 1.0-5                          3.3-55                          3.6-51 3.3-32                          3.3-56                          3.6-52 3.3-33                          3.3-57                          3.6-53 3.3-35                          3.3-58                          3.7-4 3.3-39                          3.3-59                          3.7-5 3.3-40                          3.3-60                          3.7-6 3.3-41                          3.3-64                          3.7-8 3.3-42                          3.3-77                         3.7-9 3.3-43                          3.5-1                          3.7-10 3.3-43a                          3.5-6                          3.8-16 3.3-43b                          3.5-7                         3.8-17 3.3-43c                          3.5-8                          3.8-18 3.3-43d                          3.5-9                          3.8-27 3.3-44                          3.5-10                          3.8-28 3.3-45                          3.5-11                          3.8-36 3.3-46                          3.5-12                          3.8-37 3.3-47                          3.6-3                          3.8-43
TOC Page ii TOC Page iii TOC Page iv 1.0-1 1.0-2 1.0-3 1.0-4 1.0-5 3.3-32 3.3-33 3.3-35 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-45 3.3-46 3.3-47 3.3-48 3.3-49 3.3-50 3.3-51 3.3-52 3.3-53 3.3-54 3.3-55 3.3-56 3.3-57 3.3-58 3.3-59 3.3-60 3.3-64 3.3-77 3.5-1 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 3.6-3 3.6-7 3.6-9 3.6-14 3.6-43 3.6-44 3.6-47 3.6-49 3.6-51 3.6-52 3.6-53 3.7-4 3.7-5 3.7-6 3.7-8 3.7-9 3.7-10 3.8-16 3.8-17 3.8-18 3.8-27 3.8-28 3.8-36 3.8-37 3.8-43  


TABLE OF CONTENTS B 3.3   INSTRUMENTATION (continued)
TABLE OF CONTENTS CLINTON Revision No. 2-13 iii B 3.3 INSTRUMENTATION (continued)
B 3.3.3.2   Remote Shutdown System....................................B 3.3-60 B 3.3.4.1   End of Cycle Recirculation Pump Trip (EOC-RPT)
B 3.3.3.2 Remote Shutdown System....................................B 3.3-60 B 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation...........................................B 3.3-65 B 3.3.4.2   Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B 3.3-76 B 3.3.5.1   Emergency Core Cooling System (ECCS) Instrumentation......B 3.3-85 B 3.3.5.2   Reactor Pressure Vessel (RPV) Water Inventory ControlReactor Core Isolation Cooling (RCIC) System Instrumentation ...................................... B 3.3-123122a B 3.3.5.23   Reactor Core Isolation Cooling (RCIC) System Instrumentation ...................................... B 3.3-123 B 3.3.6.1   Primary Containment and Drywell Isolation Instrumentation .........................B 3.3-135 B 3.3.6.2   Secondary Containment Isolation Instrumentation...........B 3.3-174 B 3.3.6.3   Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B 3.3-186 B 3.3.6.4   Suppression Pool Makeup (SPMU) System Instrumentation.....B 3.3-197 B 3.3.6.5   Relief and Low-Low Set (LLS) Instrumentation..............B 3.3-208 B 3.3.7.1   Control Room Ventilation (CRV) System Instrumentation.....B 3.3-215 B 3.3.8.1   Loss of Power (LOP) Instrumentation.......................B 3.3-222 B 3.3.8.2   Reactor Protection System (RPS) Electric Power Monitoring .....................................B 3.3-230 3.4     REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1       Recirculation Loops Operating.............................3.4-1 3.4.2       Flow Control Valves (FCVs)................................3.4-6 3.4.3       Jet Pumps.................................................3.4-8 3.4.4       Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5       RCS Operational LEAKAGE...................................3.4-12 3.4.6       RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7       RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8       RCS Specific Activity.....................................3.4-20 3.4.9       Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ......................................3.4-22 3.4.10       Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .....................................3.4-25 3.4.11       RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12       Reactor Steam Dome Pressure...............................3.4-33 B 3.4   REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1     Recirculation Loops Operating.............................B 3.4-1 B 3.4.2     Flow Control Valves (FCVs)................................B 3.4-9 (continued)
Instrumentation...........................................B 3.3-65 B 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B 3.3-76 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......B 3.3-85 B 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory ControlReactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123122a B 3.3.5.23 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123 B 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.........................B 3.3-135 B 3.3.6.2 Secondary Containment Isolation Instrumentation...........B 3.3-174 B 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B 3.3-186 B 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....B 3.3-197 B 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............B 3.3-208 B 3.3.7.1 Control Room Ventilation (CRV) System Instrumentation.....B 3.3-215 B 3.3.8.1 Loss of Power (LOP) Instrumentation.......................B 3.3-222 B 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.....................................B 3.3-230 3.4 REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1 Recirculation Loops Operating.............................3.4-1 3.4.2 Flow Control Valves (FCVs)................................3.4-6 3.4.3 Jet Pumps.................................................3.4-8 3.4.4 Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5 RCS Operational LEAKAGE...................................3.4-12 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7 RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8 RCS Specific Activity.....................................3.4-20 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown......................................3.4-22 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.....................................3.4-25 3.4.11 RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12 Reactor Steam Dome Pressure...............................3.4-33 B 3.4 REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1 Recirculation Loops Operating.............................B 3.4-1 B 3.4.2 Flow Control Valves (FCVs)................................B 3.4-9 (continued)  
CLINTON                                                        Revision No. 2-13 iii


TABLE OF CONTENTS B 3.4   REACTOR COOLANT SYSTEM (RCS) (continued)
TABLE OF CONTENTS CLINTON Revision No. 14-2 iv B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)
B 3.4.3     Jet Pumps.................................................B   3.4-13 B 3.4.4     Safety/Relief Valves (S/RVs)..............................B   3.4-17 B 3.4.5     RCS Operational LEAKAGE...................................B   3.4-23 B 3.4.6     RCS Pressure Isolation Valve (PIV) Leakage................B   3.4-28 B 3.4.7     RCS Leakage Detection Instrumentation.....................B   3.4-33 B 3.4.8     RCS Specific Activity.....................................B   3.4-39 B 3.4.9     Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................B 3.4-43 B 3.4.10     Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .................................B 3.4-48 B 3.4.11     RCS Pressure and Temperature (P/T) Limits.................B   3.4-53 B 3.4.12     Reactor Steam Dome Pressure...............................B   3.4-63 3.5     EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
B 3.4.3 Jet Pumps.................................................B 3.4-13 B 3.4.4 Safety/Relief Valves (S/RVs)..............................B 3.4-17 B 3.4.5 RCS Operational LEAKAGE...................................B 3.4-23 B 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................B 3.4-28 B 3.4.7 RCS Leakage Detection Instrumentation.....................B 3.4-33 B 3.4.8 RCS Specific Activity.....................................B 3.4-39 B 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown..................................B 3.4-43 B 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................B 3.4-48 B 3.4.11 RCS Pressure and Temperature (P/T) Limits.................B 3.4-53 B 3.4.12 Reactor Steam Dome Pressure...............................B 3.4-63 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM..............................3.5-1 3.5.1       ECCS - Operating ...........................................3.5-1 3.5.2       RPV Water Inventory ControlECCS - Shutdown .................3.5-6 3.5.3       RCIC System...............................................3.5-1011 B 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM..............................3.5-1 3.5.1 ECCS - Operating...........................................3.5-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown.................3.5-6 3.5.3 RCIC System...............................................3.5-1011 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................B 3.5-1 B 3.5.1     ECCS - Operating ...........................................B 3.5-1 B 3.5.2     ECCS - ShutdownRPV Water Inventory Control .................B 3.5-1517 B 3.5.3     RCIC System...............................................B 3.5-2127 3.6     CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1     Primary Containment.......................................3.6-1 3.6.1.2     Primary Containment Air Locks.............................3.6-3 3.6.1.3     Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4     Primary Containment Pressure..............................3.6-20 3.6.1.5     Primary Containment Air Temperature.......................3.6-21 3.6.1.6     Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7     Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8     Deleted...................................................3.6-26 3.6.1.9     Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1     Suppression Pool Average Temperature......................3.6-28 3.6.2.2     Suppression Pool Water Level..............................3.6-31 3.6.2.3     Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4     Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1     Deleted .................................................3.6-36 3.6.3.2     Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................B 3.5-1 B 3.5.1 ECCS - Operating...........................................B 3.5-1 B 3.5.2 ECCS - ShutdownRPV Water Inventory Control.................B 3.5-1517 B 3.5.3 RCIC System...............................................B 3.5-2127 3.6 CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1 Primary Containment.......................................3.6-1 3.6.1.2 Primary Containment Air Locks.............................3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4 Primary Containment Pressure..............................3.6-20 3.6.1.5 Primary Containment Air Temperature.......................3.6-21 3.6.1.6 Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7 Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8 Deleted...................................................3.6-26 3.6.1.9 Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1 Suppression Pool Average Temperature......................3.6-28 3.6.2.2 Suppression Pool Water Level..............................3.6-31 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4 Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1 Deleted.................................................3.6-36 3.6.3.2 Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)  
CLINTON                                                          Revision No. 14-2 iv


Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions
Definitions 1.1 CLINTON 1.0-1 Amendment No. 105 1.0 USE AND APPLICATION 1.1 Definitions  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term                       Definition ACTIONS                     ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR       The APLHGR shall be applicable to a specific HEAT GENERATION RATE       planar height and is equal to the sum of the (APLHGR)                   LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR)
CHANNEL CALIBRATION         A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.
LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL CHECK               A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST     A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
(continued)
(continued)  
CLINTON                              1.0-1                  Amendment No. 105


Definitions 1.1 1.1 Definitions (continued)
Definitions 1.1 CLINTON 1.0-2 Amendment No. 105 1.1 Definitions (continued)
CORE ALTERATION             CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
and
and
: b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
: b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS       The COLR is the unit specific document that REPORT (COLR)               provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131       DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.
DRAIN TIME                 The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
: a. The water inventory above the TAF is divided by the limiting drain rate;
: a.
: b. The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,
The water inventory above the TAF is divided by the limiting drain rate;
: b.
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,
seismic event, loss of normal power, single human error), for all (continued)
seismic event, loss of normal power, single human error), for all (continued)
CLINTON                              1.0-2                    Amendment No. 105


Definitions 1.1 Definitions DRAIN TIME                 penetration flow paths below the TAF except:
Definitions 1.1 CLINTON 1.0-3 Amendment No. 105 Definitions DRAIN TIME penetration flow paths below the TAF except:
(continued)
(continued)
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
Line 130: Line 136:
: e. Realistic cross-sectional areas and drain rates are used.
: e. Realistic cross-sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in lieu of a calculated value.
A bounding DRAIN TIME may be used in lieu of a calculated value.
EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME                   initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
(continued)
CLINTON                        1.0-3                    Amendment No. 105


Definitions 1.1 1.1 Definitions (continued)
Definitions 1.1 CLINTON 1.0-4 Amendment No. 105 1.1 Definitions (continued)
END OF CYCLE               The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP     time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE   associated turbine stop valve or turbine TIME                       control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE associated turbine stop valve or turbine TIME control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
INSERVICE TESTING           The INSERVICE TESTING PROGRAM is the licensee PROGRAM                     program that fulfills the requirements of 10 CFR 50.55a(f).
INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).
ISOLATION SYSTEM           The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME               time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
LEAKAGE                     LEAKAGE shall be:
LEAKAGE LEAKAGE shall be:
: a. Identified LEAKAGE
: a. Identified LEAKAGE
: 1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
: 1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
Line 145: Line 150:
: c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
: c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
(continued)
(continued)  
CLINTON                              1.0-4                  Amendment No. 105


Definitions 1.1 1.1   Definitions (continued)
Definitions 1.1 CLINTON 1.0-5 Amendment No. 95 128 1.1 Definitions (continued)
LINEAR HEAT GENERATION       The LHGR shall be the heat generation rate per RATE (LHGR)                 unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL     A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST                         of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
MINIMUM CRITICAL POWER       The MCPR shall be the smallest critical power RATIO (MCPR)                 ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MODE                         A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLE OPERABILITY       A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
OPERABLE OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RATED THERMAL POWER         RTP shall be a total reactor core heat transfer (RTP)                       rate to the reactor coolant of 3473 MWt.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3473 MWt.
REACTOR PROTECTION           The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE       from when the monitored parameter exceeds its RPS TIME                         trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
(continued)  
CLINTON                              1.0-5                  Amendment No. 95 128


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-32 Amendment No. 95 ACTIONS (continued)
CONDITION               REQUIRED ACTION         COMPLETION TIME B. As required by     B.1   --------NOTES---------
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action A.1      1. Only applicable and referenced in              in MODES 1, 2, Table 3.3.5.1-1.              and 3.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
B.1  
--------NOTES---------
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.
: 2. Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.
Declare supported         1 hour from feature(s) inoperable     discovery of when its redundant       loss of feature ECCS initiation  initiation capability is             capability for inoperable.              feature(s) in both divisions AND B.2   --------NOTES---------
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions B.2  
--------NOTES---------
: 1. Only applicable in MODES 1, 2, and 3.
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 3.a and 3.b.
: 2. Only applicable for Functions 3.a and 3.b.
Declare High Pressure     1 hour from Core Spray (HPCS)         discovery of System inoperable.       loss of HPCS initiation capability AND B.3   Place channel in trip. 24 hours (continued)
Declare High Pressure Core Spray (HPCS)
CLINTON                        3.3-32                      Amendment No. 95
System inoperable.
AND B.3 Place channel in trip.
1 hour from discovery of loss of HPCS initiation capability 24 hours (continued)  


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-33 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME C. As required by     C.1   ---------NOTES--------
CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Action A.1      1. Only applicable and referenced in              in MODES 1, 2, Table 3.3.5.1-1.              and 3.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
C.1  
---------NOTES--------
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 1.c, 1.d, 2.c, and 2.d.
: 2. Only applicable for Functions 1.c, 1.d, 2.c, and 2.d.
Declare supported         1 hour from feature(s) inoperable     discovery of when its redundant       loss of feature ECCS             initiation initiation capability     capability for is inoperable.           feature(s) in both divisions AND C.2   Restore channel to       24 hours OPERABLE status.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
(continued)
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions C.2 Restore channel to OPERABLE status.
CLINTON                        3.3-33                      Amendment No. 95
24 hours (continued)  


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-35 Amendment No. 95 ACTIONS (continued)
CONDITION               REQUIRED ACTION         COMPLETION TIME E. As required by     E.1   --------NOTES---------
CONDITION REQUIRED ACTION COMPLETION TIME E.
Required Action A.1      1. Only applicable in and referenced in            MODES 1, 2, and 3.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Table 3.3.5.1-1.
E.1  
--------NOTES---------
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 1.e, 1.f, and 2.e.
: 2. Only applicable for Functions 1.e, 1.f, and 2.e.
Declare supported         1 hour from feature(s) inoperable     discovery of when its redundant       loss of feature ECCS             initiation initiation capability     capability for is inoperable.           feature(s) in both divisions AND E.2   Restore channel to       7 days OPERABLE status.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
(continued)
AND E.2 Restore channel to OPERABLE status.
CLINTON                        3.3-35                      Amendment No. 95
1 hour from discovery of loss of initiation capability for feature(s) in both divisions 7 days (continued)  


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-39 Amendment No. 169 Table 3.3.5.1-1 (page 1 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES OR                   REFERENCED OTHER           REQUIRED   FROM SPECIFIED          CHANNELS REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS             PER  ACTION A.1   REQUIREMENTS         VALUE FUNCTION
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
Subsystems
: a. Reactor Vessel Water         1,2,3,             2(ba)       B     SR   3.3.5.1.1     -148.1 Level-Low Low Low,                                                SR   3.3.5.1.2     inches (a)    (a)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3, 4(a),5(a) 2(ba)
Level 1                      4    ,5                            SR   3.3.5.1.3(ec)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR   3.3.5.1.5 SR   3.3.5.1.6(ec)
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)  
: b. Drywell Pressure-High         1,2,3             2(ba)       B     SR   3.3.5.1.1     1.88 psig SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
-148.1 inches
: c. LPCI Pump A                 1,2,3,               1         C     SR   3.3.5.1.2     4.5 seconds Start-Time Delay                                                  SR   3.3.5.1.4     and (a)    (a)
: b. Drywell Pressure-High 1,2,3 2(ba)
Logic Card                  4    ,5                            SR   3.3.5.1.5     5.5 seconds
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
: d. Reactor Vessel               1,2,3               4       C     SR   3.3.5.1.1     454 psig Pressure-Low                                                      SR   3.3.5.1.2     and (Injection Permissive)                                            SR   3.3.5.1.3(ec) 494 psig SR   3.3.5.1.4(ec)
: c. LPCI Pump A Start-Time Delay Logic Card 1,2,3, 4(a),5(a) 1 C
SR   3.3.5.1.5 4(a),5(a)           4         B     SR   3.3.5.1.1     454 psig SR   3.3.5.1.2     and SR   3.3.5.1.3(e)   494 psig SR   3.3.5.1.4(e)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds
SR   3.3.5.1.5
: d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4
: e. LPCS Pump Discharge         1,2,3,               1         E     SR   3.3.5.1.1     750 gpm Flow-Low (Bypass)                                                SR   3.3.5.1.2 4(a),5(a)                            SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: f. LPCI Pump A Discharge       1,2,3,               1         E     SR   3.3.5.1.1     900 gpm Flow-Low (Bypass)                                                SR   3.3.5.1.2 (a)    (a) 4    ,5                            SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.4(ec)
: g. Manual Initiation           1,2,3,               1         C     SR   3.3.5.1.5     NA (a)    (a) 4    ,5 (continued)
SR 3.3.5.1.5 454 psig and 494 psig 4(a),5(a) 4 B
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(e)
SR 3.3.5.1.4(e)
SR 3.3.5.1.5 454 psig and 494 psig
: e. LPCS Pump Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 750 gpm
: f. LPCI Pump A Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm
: g. Manual Initiation 1,2,3, 4(a),5(a) 1 C
SR 3.3.5.1.5 NA (continued)
(a) When associated subsystem(s) are required to be OPERABLE.
(a) When associated subsystem(s) are required to be OPERABLE.
(ba) Also required to initiate the associated diesel generator.
(ba) Also required to initiate the associated diesel generator.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                          3.3-39                          Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-40 Amendment No. 169 Table 3.3.5.1-1 (page 2 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                     CONDITIONS MODES OR                     REFERENCED OTHER           REQUIRED       FROM SPECIFIED        CHANNELS PER   REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS         FUNCTION    ACTION A.1   REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. LPCI B and LPCI C Subsystems
: 2. LPCI B and LPCI C Subsystems
: a. Reactor Vessel           1,2,3,             2(ba)         B     SR   3.3.5.1.1     -148.1 Water Level-Low Low                                              SR   3.3.5.1.2     inches (a)    (a)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3, 4(a),5(a) 2(ba)
Low, Level 1              4    ,5                                SR   3.3.5.1.3(ec)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR   3.3.5.1.5 SR   3.3.5.1.6(ec)
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)  
: b. Drywell Pressure-         1,2,3             2(ba)         B     SR   3.3.5.1.1     1.88 psig High                                                              SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
-148.1 inches
: c. LPCI Pump B               1,2,3,               1           C     SR   3.3.5.1.2     4.5 seconds Start-Time Delay                                                  SR   3.3.5.1.4     and (a)    (a)
: b. Drywell Pressure-High 1,2,3 2(ba)
Logic Card                4    ,5                                SR   3.3.5.1.5     5.5 seconds
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
: d. Reactor Vessel             1,2,3               4           C     SR   3.3.5.1.1     454 psig Pressure-Low                                                      SR   3.3.5.1.2     and (Injection                                                        SR   3.3.5.1.3(ec) 494 psig Permissive)                                                      SR   3.3.5.1.4(ec)
: c. LPCI Pump B Start-Time Delay Logic Card 1,2,3, 4(a),5(a) 1 C
SR   3.3.5.1.5 4(a),5(a)           4           B     SR   3.3.5.1.1     454 psig SR   3.3.5.1.2     and SR   3.3.5.1.3(e)   494 psig SR   3.3.5.1.4(e)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds
SR   3.3.5.1.5
: d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4
: e. LPCI Pump B and           1,2,3,         1 per pump       E     SR   3.3.5.1.1     900 gpm LPCI Pump C                                                      SR   3.3.5.1.2 Discharge Flow-Low        4(a),5(a)                              SR   3.3.5.1.3 (Bypass)                                                          SR   3.3.5.1.4 SR   3.3.5.1.5
C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: f. Manual Initiation         1,2,3,               1           C     SR   3.3.5.1.5     NA 4(a),5(a)
SR 3.3.5.1.4(ec)
(continued)
SR 3.3.5.1.5 454 psig and 494 psig 4(a),5(a) 4 B
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(e)
SR 3.3.5.1.4(e)
SR 3.3.5.1.5 454 psig and 494 psig
: e. LPCI Pump B and LPCI Pump C Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 per pump E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm
: f. Manual Initiation 1,2,3, 4(a),5(a) 1 C
SR 3.3.5.1.5 NA (continued)
(a) When associated subsystem(s) are required to be OPERABLE.
(a) When associated subsystem(s) are required to be OPERABLE.
(ba) Also required to initiate the associated diesel generator.
(ba) Also required to initiate the associated diesel generator.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                        3.3-40                            Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-41 Amendment No. 169 Table 3.3.5.1-1 (page 3 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                     CONDITIONS MODES OR                     REFERENCED OTHER         REQUIRED       FROM SPECIFIED      CHANNELS PER   REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS         FUNCTION    ACTION A.1   REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. High Pressure Core Spray (HPCS) System
: 3. High Pressure Core Spray (HPCS) System
: a. Reactor Vessel Water       1,2,3,             4(ba)         B     SR   3.3.5.1.1     -48.1 inches Level-Low Low,                                                    SR   3.3.5.1.2 (a)    (a)
: a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3, 4(a),5(a) 4(ba)
Level 2                    4    ,5                              SR   3.3.5.1.3(ec)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR   3.3.5.1.5 SR   3.3.5.1.6(ec)
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)  
: b. Drywell                     1,2,3             4(ba)         B     SR   3.3.5.1.1     1.88 psig Pressure - High                                                  SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
-48.1 inches
: c. Reactor Vessel Water       1,2,3,             2           C     SR   3.3.5.1.1     54.6 inches Level-High,                                                      SR   3.3.5.1.2 (a)    (a)
: b. Drywell Pressure - High 1,2,3 4(ba)
Level 8                    4    ,5                              SR   3.3.5.1.3(ec)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR   3.3.5.1.5 SR   3.3.5.1.6(ec)
: c. Reactor Vessel Water Level-High, Level 8 1,2,3, 4(a),5(a) 2 C
: d. RCIC Storage Tank         1,2,3,             2           D     SR   3.3.5.1.1     3.0 inches Level-Low                                                        SR   3.3.5.1.2 (c)    (c) 4    ,5                              SR   3.3.5.1.3(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR   3.3.5.1.4(ec)
SR 3.3.5.1.5 SR 3.3.5.1.6(ec) 54.6 inches
SR   3.3.5.1.5
: d. RCIC Storage Tank Level-Low 1,2,3, 4(c),5(c) 2 D
: e. Suppression Pool           1,2,3             2           D     SR   3.3.5.1.1     11 inches Water Level-High                                                  SR   3.3.5.1.2 SR   3.3.5.1.3(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR   3.3.5.1.4(ec)
SR 3.3.5.1.4(ec)
SR   3.3.5.1.5
SR 3.3.5.1.5 3.0 inches
: f. HPCS Pump                 1,2,3,             1           E     SR   3.3.5.1.1     120 psig Discharge                                                        SR   3.3.5.1.2 (a)    (a)
: e. Suppression Pool Water Level-High 1,2,3 2
Pressure-High              4    ,5                              SR   3.3.5.1.3 (Bypass)                                                          SR   3.3.5.1.4 SR   3.3.5.1.5
D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: g. HPCS System Flow           1,2,3,             1           E     SR   3.3.5.1.1     500 gpm Rate-Low (Bypass)                                                SR   3.3.5.1.2 (a)    (a) 4    ,5                              SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.4(ec)
: h. Manual Initiation         1,2,3,             1           C     SR   3.3.5.1.5     NA 4(a),5(a)
SR 3.3.5.1.5 11 inches
(continued)
: f. HPCS Pump Discharge Pressure-High (Bypass) 1,2,3, 4(a),5(a) 1 E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 120 psig
: g. HPCS System Flow Rate-Low (Bypass) 1,2,3, 4(a),5(a) 1 E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 500 gpm
: h. Manual Initiation 1,2,3, 4(a),5(a) 1 C
SR 3.3.5.1.5 NA (continued)
(a) When associated subsystem(s) are required to be OPERABLE.
(a) When associated subsystem(s) are required to be OPERABLE.
(ba) Also required to initiate the associated diesel generator.
(ba) Also required to initiate the associated diesel generator.
Line 257: Line 291:
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                        3.3-41                            Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-42 Amendment No. 169 Table 3.3.5.1-1 (page 4 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES OR                   REFERENCED OTHER       REQUIRED       FROM SPECIFIED    CHANNELS PER   REQUIRED      SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS       FUNCTION    ACTION A.1     REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
: 4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
: a. Reactor Vessel Water   1,2(db),3(db)       2           F     SR   3.3.5.1.1     -148.1 inches Level-Low Low Low,                                              SR   3.3.5.1.2 Level 1                                                        SR   3.3.5.1.3(ec)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(db),3(db) 2 F
SR   3.3.5.1.5 SR   3.3.5.1.6(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: b. Drywell               1,2(db),3(db)       2           F     SR   3.3.5.1.1     1.88 psig Pressure-High                                                  SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)  
: c. ADS Initiation Timer   1,2(db),3(db)       1           G     SR   3.3.5.1.2     117 seconds SR   3.3.5.1.4 SR   3.3.5.1.5
-148.1 inches
: d. Reactor Vessel Water   1,2(db),3(db)       1           F     SR   3.3.5.1.1     8.3 inches Level-Low, Level 3                                              SR   3.3.5.1.2 (Confirmatory)                                                  SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
: b. Drywell Pressure-High 1,2(db),3(db) 2 F
: e. LPCS Pump Discharge   1,2(db),3(db)       2           G     SR   3.3.5.1.1     125 psig and Pressure-High                                                  SR   3.3.5.1.2     < 176.3 psig SR   3.3.5.1.3(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR   3.3.5.1.4(ec)
: c. ADS Initiation Timer 1,2(db),3(db) 1 G
SR   3.3.5.1.5
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds
: f. LPCI Pump A           1,2(db),3(db)       2           G     SR   3.3.5.1.1     115 psig and Discharge Pressure-                                            SR   3.3.5.1.2     < 135 psig High                                                            SR   3.3.5.1.3(ec)
: d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(db),3(db) 1 F
SR   3.3.5.1.4(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches
SR   3.3.5.1.5
: e. LPCS Pump Discharge Pressure-High 1,2(db),3(db) 2 G
: g. ADS Drywell Pressure   1,2(db),3(db)       2           G     SR   3.3.5.1.2     6.5 minutes Bypass Timer                                                    SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: h. Manual Initiation     1,2(db),3(db)       2           G     SR   3.3.5.1.5     NA (continued)
SR 3.3.5.1.4(ec)
SR 3.3.5.1.5 125 psig and
< 176.3 psig
: f. LPCI Pump A Discharge Pressure-High 1,2(db),3(db) 2 G
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR 3.3.5.1.4(ec)
SR 3.3.5.1.5 115 psig and
< 135 psig
: g. ADS Drywell Pressure Bypass Timer 1,2(db),3(db) 2 G
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes
: h. Manual Initiation 1,2(db),3(db) 2 G
SR 3.3.5.1.5 NA (continued)
(d) (b) With reactor steam dome pressure > 150 psig.
(d) (b) With reactor steam dome pressure > 150 psig.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                      3.3-42                              Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-43 Amendment No. 169 Table 3.3.5.1-1 (page 5 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER       REQUIRED     FROM SPECIFIED    CHANNELS PER REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS     FUNCTION  ACTION A.1   REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. ADS Trip System 2 (Logic B and F)
: 5. ADS Trip System 2 (Logic B and F)
: a. Reactor Vessel Water     1,2(db),3(db)       2           F     SR 3.3.5.1.1     -148.1 Level-Low Low Low,                                              SR 3.3.5.1.2     inches Level 1                                                        SR 3.3.5.1.3(ec)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(db),3(db) 2 F
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
: b. Drywell Pressure-High     1,2(db),3(db)       2           F     SR 3.3.5.1.1     1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(ec)  
: c. ADS Initiation Timer     1,2(db),3(db)       1           G     SR 3.3.5.1.2     117 seconds SR 3.3.5.1.4 SR 3.3.5.1.5
-148.1 inches
: d. Reactor Vessel Water     1,2(db),3(db)       1           F     SR 3.3.5.1.1     8.3 inches Level-Low, Level 3                                              SR 3.3.5.1.2 (Confirmatory)                                                  SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5
: b. Drywell Pressure-High 1,2(db),3(db) 2 F
: e. LPCI Pumps B & C         1,2(db),3(db) 2 per pump       G     SR 3.3.5.1.1     115 psig Discharge                                                      SR 3.3.5.1.2     and  135 Pressure-High                                                  SR 3.3.5.1.3(ec) psig SR 3.3.5.1.4(ec)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR 3.3.5.1.5
: c. ADS Initiation Timer 1,2(db),3(db) 1 G
: f. ADS Drywell Pressure     1,2(db),3(db)       2           G     SR 3.3.5.1.2     6.5 minutes Bypass Timer                                                    SR 3.3.5.1.4 SR 3.3.5.1.5
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds
: g. Manual Initiation         1,2(db),3(db)       2           G     SR 3.3.5.1.5     NA (db) With reactor steam dome pressure > 150 psig.
: d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(db),3(db) 1 F
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches
: e. LPCI Pumps B & C Discharge Pressure-High 1,2(db),3(db) 2 per pump G
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)
SR 3.3.5.1.4(ec)
SR 3.3.5.1.5 115 psig and 135 psig
: f. ADS Drywell Pressure Bypass Timer 1,2(db),3(db) 2 G
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes
: g. Manual Initiation 1,2(db),3(db) 2 G
SR 3.3.5.1.5 NA (db) With reactor steam dome pressure > 150 psig.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
CLINTON                                      3.3-43                          Amendment No. 169


RPV Water Inventory Control Instrumentation 3.3.5.2 3.3   INSTRUMENTATION 3.3.5.2       Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2       The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43a Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
APPLICABILITY:     According to Table 3.3.5.2-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.5.2-1.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. One or more channels   A.1   Enter the Condition       Immediately inoperable.                    referenced in Table 3.3.5.2-1 for the channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
B. As required by         B.1    Declare associated        Immediately Required Action A.1           penetration flow and referenced in             path(s) incapable of Table 3.3.5.2-1.               automatic isolation.
A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel.
AND B.2   Calculate DRAIN TIME. Immediately C. As required by         C.1    Place channel in trip. 1 hour Required Action A.1 and referenced in Table 3.3.5.2-1.
Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
(continued)
B.1 Declare associated penetration flow path(s) incapable of automatic isolation.
CLINTON                          3.3-43a                      Amendment No. 95
AND B.2 Calculate DRAIN TIME.
Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
C.1 Place channel in trip.
1 hour (continued)  


RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43b Amendment No. 95 ACTIONS (continued)
CONDITION             REQUIRED ACTION           COMPLETION TIME D. As required by       D.1  Declare HPCS system      1 hour Required Action A.1       inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
and referenced in Table 3.3.5.2-1. OR D.2 Align the HPCS pump       1 hour suction to the suppression pool.
D.1 Declare HPCS system inoperable.
E. As required by       E.1  Restore channel to        24 hours Required Action A.1       OPERABLE status.
OR D.2 Align the HPCS pump suction to the suppression pool.
and referenced in Table 3.3.5.2-1.
1 hour 1 hour E. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
F. Required Action and F.1  Declare associated        Immediately associated               ECCS injection/spray Completion Time of       subsystem inoperable.
E.1 Restore channel to OPERABLE status.
Condition C, D, or E not met.
24 hours F. Required Action and associated Completion Time of Condition C, D, or E not met.
CLINTON                      3.3-43b                      Amendment No. 95
F.1 Declare associated ECCS injection/spray subsystem inoperable.
Immediately


RPV Water Inventory Control Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43c Amendment No. 9 5 SURVEILLANCE REQUIREMENTS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE                             FREQUENCY SR 3.3.5.2.1   Perform CHANNEL CHECK.                       In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2   Perform CHANNEL FUNCTIONAL TEST.             In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3   Perform LOGIC SYSTEM FUNCTIONAL TEST.         In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-43c                    Amendment No. 9    5
SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program  


RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 2)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43d Amendment No. 95 Table 3.3.5.2-1 (page 1 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE                 CONDITIONS MODES OR     REQUIRED   REFERENCED OTHER      CHANNELS     FROM SPECIFIED        PER     REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION           CONDITIONS     FUNCTION  ACTION A.1 REQUIREMENTS     VALUE
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
Subsystems
: a. Reactor                 4,5           4(a)         C   SR 3.3.5.2.1 494 psig Vessel Pressure -                                        SR 3.3.5.2.2 Low (Injection Permissive)
: a.
: b. LPCS Pump               4,5         1 per         E     SR 3.3.5.2.1 750 gpm Discharge Flow -                    pump(a)              SR 3.3.5.2.2 Low (Bypass)
Reactor Vessel Pressure -
: c. LPCI Pump A             4,5         1 per         E     SR 3.3.5.2.1 900 gpm Discharge Flow -                    pump(a)              SR 3.3.5.2.2 Low (Bypass)
Low (Injection Permissive) 4,5 4(a)
C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig
: b. LPCS Pump Discharge Flow -
Low (Bypass) 4,5 1 per pump(a)
E SR 3.3.5.2.1 SR 3.3.5.2.2 750 gpm
: c. LPCI Pump A Discharge Flow -
Low (Bypass) 4,5 1 per pump(a)
E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm
: 2. LPCI B and LPCI C Subsystems
: 2. LPCI B and LPCI C Subsystems
: a. Reactor Vessel           4,5         4(a)         C     SR 3.3.5.2.1   494 psig Pressure - Low                                            SR 3.3.5.2.2 (Injection Permissive)
: a. Reactor Vessel Pressure - Low (Injection Permissive) 4,5 4(a)
: b. LPCI Pump B             4,5         1 per         E     SR 3.3.5.2.1   900 gpm and LPCI Pump C                    pump(a)              SR 3.3.5.2.2 Discharge Flow -
C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig
Low (Bypass)
: b. LPCI Pump B and LPCI Pump C Discharge Flow -
(continued)
Low (Bypass) 4,5 1 per pump(a)
(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm (continued)
CLINTON                                    3.3-43d                        Amendment No.      95
(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."  


RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 2 of 2)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-44 Amendment No.
RPV Water Inventory Control Instrumentation APPLICABLE                 CONDITIONS MODES OR     REQUIRED   REFERENCED OTHER      CHANNELS       FROM SPECIFIED        PER       REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS     FUNCTION    ACTION A.1   REQUIREMENTS       VALUE
Table 3.3.5.2-1 (page 2 of 2)
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. High Pressure Core Spray (HPCS) System
: 3. High Pressure Core Spray (HPCS) System
: a. RCIC Storage Tank     4(b), 5(b)       2(a)         D     SR   3.3.5.2.1     3.0 inches Level - Low                                                SR   3.3.5.2.2
: a. RCIC Storage Tank Level - Low 4(b), 5(b) 2(a)
: b. HPCS Pump               4, 5         1(a)         E     SR   3.3.5.2.1     120 psig Discharge                                                  SR   3.3.5.2.2 Pressure - High (Bypass)
D SR 3.3.5.2.1 SR 3.3.5.2.2 3.0 inches
: c. HPCS System Flow         4, 5         1(a)         E     SR   3.3.5.2.1     500 gpm Rate - Low                                                SR   3.3.5.2.2 (Bypass)
: b. HPCS Pump Discharge Pressure - High (Bypass) 4, 5 1(a)
: 4. RHR System Isolation 8.3 inches (c)
E SR 3.3.5.2.1 SR 3.3.5.2.2 120 psig
: a. Reactor Vessel                     2 in one       B     SR   3.3.5.2.1 Water Level -                        trip                SR   3.3.5.2.2 Low, Level 3                         system
: c. HPCS System Flow Rate - Low (Bypass) 4, 5 1(a)
E SR 3.3.5.2.1 SR 3.3.5.2.2 500 gpm
: 4. RHR System Isolation
: a. Reactor Vessel Water Level -
Low, Level 3 (c) 2 in one trip system B
SR 3.3.5.2.1 SR 3.3.5.2.2 8.3 inches
: 5. Reactor Water Cleanup (RWCU) System Isolation
: 5. Reactor Water Cleanup (RWCU) System Isolation
                                                                                        -48.1 (c)
: a. Reactor Vessel Water Level - Low Low, Level 2 (c) 2 in one trip system B
: a. Reactor Vessel                     2 in one       B     SR   3.3.5.2.1 Water Level - Low                    trip                SR   3.3.5.2.2   inches Low, Level 2                        system (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
SR 3.3.5.2.1 SR 3.3.5.2.2  
-48.1 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.
(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.
(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
CLINTON                                      3.3-44                                  Amendment No.


RCIC System Instrumentation 3.3.5.32 3.3 INSTRUMENTATION 3.3.5.2 3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.23   The RCIC System instrumentation for each Function in Table 3.3.5.23-1 shall be OPERABLE.
RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-45 Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.23 The RCIC System instrumentation for each Function in Table 3.3.5.23-1 shall be OPERABLE.
APPLICABILITY:   MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
ACTIONS  
------------------------------------NOTE--------------------------------------
------------------------------------NOTE--------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                 REQUIRED ACTION         COMPLETION TIME A. One or more channels A.1   Enter the Condition       Immediately inoperable.                referenced in Table 3.3.5.23-1 for the channel.
CONDITION REQUIRED ACTION COMPLETION TIME A.
B. As required by       B.1  Declare RCIC System      1 hour from Required Action A.1         inoperable.              discovery of and referenced in                                     loss of RCIC Table 3.3.5.23-1.                                     initiation capability AND B.2   Place channel in         24 hours trip.
One or more channels inoperable.
C. As required by       C.1  Restore channel to        24 hours Required Action A.1         OPERABLE status.
A.1 Enter the Condition referenced in Table 3.3.5.23-1 for the channel.
and referenced in Table 3.3.5.23-1.
Immediately B.
(continued)
As required by Required Action A.1 and referenced in Table 3.3.5.23-1.
CLINTON                          3.3-45                        Amendment No. 95
B.1 Declare RCIC System inoperable.
AND B.2 Place channel in trip.
1 hour from discovery of loss of RCIC initiation capability 24 hours C.
As required by Required Action A.1 and referenced in Table 3.3.5.23-1.
C.1 Restore channel to OPERABLE status.
24 hours (continued)  


RCIC System Instrumentation 3.3.5.32 ACTIONS (continued)
RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-46 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME D. As required by       D.1   ---------NOTE----------
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action A.1        Only applicable if and referenced in          RCIC pump suction is Table 3.3.5.23-1.          not aligned to the suppression pool.
As required by Required Action A.1 and referenced in Table 3.3.5.23-1.
Declare RCIC System       1 hour from inoperable.               discovery of loss of RCIC initiation capability AND D.2.1 Place channel in         24 hours trip.
D.1  
OR D.2.2 Align RCIC pump           24 hours suction to the suppression pool.
---------NOTE----------
E. Required Action and   E.1  Declare RCIC System      Immediately associated Completion       inoperable.
Only applicable if RCIC pump suction is not aligned to the suppression pool.
Time of Condition B, C, or D not met.
Declare RCIC System inoperable.
CLINTON                        3.3-46                      Amendment No. 95
AND D.2.1 Place channel in trip.
OR D.2.2 Align RCIC pump suction to the suppression pool.
1 hour from discovery of loss of RCIC initiation capability 24 hours 24 hours E.
Required Action and associated Completion Time of Condition B, C, or D not met.
E.1 Declare RCIC System inoperable.
Immediately


RCIC System Instrumentation 3.3.5.32 SURVEILLANCE REQUIREMENTS
RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-47 Amendment No. 192 SURVEILLANCE REQUIREMENTS  
------------------------------------NOTES-------------------------------------
------------------------------------NOTES-------------------------------------
: 1. Refer to Table 3.3.5.23-1 to determine which SRs apply for each RCIC Function.
: 1. Refer to Table 3.3.5.23-1 to determine which SRs apply for each RCIC Function.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 5; and (b) for up to 6 hours for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 5; and (b) for up to 6 hours for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.
SURVEILLANCE                             FREQUENCY SR 3.3.5.23.1   Perform CHANNEL CHECK.                     In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.2   Perform CHANNEL FUNCTIONAL TEST.           In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.3   Calibrate the analog trip module.           In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.4   Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.5   Perform LOGIC SYSTEM FUNCTIONAL TEST.       In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.6   Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-47                      Amendment No. 192
SURVEILLANCE FREQUENCY SR 3.3.5.23.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.3 Calibrate the analog trip module.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.4 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.6 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program  


RCIC System Instrumentation 3.3.5.32 Table 3.3.5.23-1 (page 1 of 1)
RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-48 Amendment No. 169 Table 3.3.5.23-1 (page 1 of 1)
Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED    REFERENCED FROM CHANNELS PER  REQUIRED ACTION     SURVEILLANCE      ALLOWABLE FUNCTION              FUNCTION            A.1           REQUIREMENTS         VALUE
Reactor Core Isolation Cooling System Instrumentation FUNCTION REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Reactor Vessel Water             4               B           SR 3.3.5.23.1   -48.1 inches Level-Low Low, Level 2                                        SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.5 SR 3.3.5.23.6
: 1. Reactor Vessel Water Level-Low Low, Level 2 4
: 2. Reactor Vessel Water             2               C           SR 3.3.5.23.1   52.6 inches Level-High, Level 8                                            SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5
B SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.5 SR 3.3.5.23.6  
: 3. RCIC Storage Tank                 2               D           SR 3.3.5.23.1   3.0 inches Level-Low                                                      SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5
-48.1 inches
: 4. Suppression Pool Water           2               D           SR 3.3.5.23.1   -5 inches Level-High                                                    SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5
: 2. Reactor Vessel Water Level-High, Level 8 2
: 5. Manual Initiation                 1               C           SR 3.3.5.23.5 NA CLINTON                                      3.3-48                        Amendment No. 169
C SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5 52.6 inches
: 3. RCIC Storage Tank Level-Low 2
D SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5 3.0 inches
: 4. Suppression Pool Water Level-High 2
D SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5  
-5 inches
: 5. Manual Initiation 1
C SR 3.3.5.23.5 NA  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1     The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-49 Amendment No. 95 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1 The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:   According to Table 3.3.6.1-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.6.1-1.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                   REQUIRED ACTION         COMPLETION TIME
CONDITION REQUIRED ACTION COMPLETION TIME  
-----------NOTE----------     A.1    Place one channel in  48 hours Only applicable to Main               affected Function in Steam Line (MSL) isolation           trip.
-----------NOTE----------
Functions.
Only applicable to Main Steam Line (MSL) isolation Functions.
A. One or more Functions with one channel inoperable.
A. One or more Functions with one channel inoperable.
-----------NOTE----------     B.1    Place one channel in  6 hours Only applicable to MSL               affected Function in isolation Functions.                  trip.
A.1 Place one channel in affected Function in trip.
B. One or more Functions with two channels inoperable.
48 hours
-----------NOTE----------     C.1    Restore two channels  1 hour Only applicable to MSL               in affected Function isolation Functions.                  to OPERABLE status.
-----------NOTE----------
Only applicable to MSL isolation Functions.
B.
One or more Functions with two channels inoperable.
B.1 Place one channel in affected Function in trip.
6 hours
-----------NOTE----------
Only applicable to MSL isolation Functions.
C. One or more Functions with three or more channels inoperable.
C. One or more Functions with three or more channels inoperable.
(continued)
C.1 Restore two channels in affected Function to OPERABLE status.
CLINTON                            3.3-49                      Amendment No. 95
1 hour (continued)


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-50 Amendment No. 95 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME
CONDITION REQUIRED ACTION COMPLETION TIME  
------------NOTE----------   D.1    Place channel in trip. 24 hours Not applicable to MSL isolation Functions.
------------NOTE----------
Not applicable to MSL isolation Functions.
D. One or more required channels inoperable.
D. One or more required channels inoperable.
------------NOTE---------   E.1    Restore isolation      1 hour Not applicable to MSL               capability.
D.1 Place channel in trip.
isolation Functions.
24 hours
------------NOTE---------
Not applicable to MSL isolation Functions.
E. One or more automatic Functions with isolation capability not maintained.
E. One or more automatic Functions with isolation capability not maintained.
F. Required Action and     F.1     Enter the Condition     Immediately associated Completion            referenced in Time of Condition A,            Table 3.3.6.1-1 for B, C, D, or E not                the channel.
E.1 Restore isolation capability.
met.
1 hour F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.
G. As required by           G.1    Isolate associated      12 hours Required Action F.1             MSL.
F.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.
and referenced in Table 3.3.6.1-1.         OR G.2.1   Be in MODE 3.           12 hours AND G.2.2   Be in MODE 4.           36 hours H. As required by           H.1     Be in MODE 2.           6 hours Required Action F.1 and referenced in Table 3.3.6.1-1.
Immediately G. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
I. As required by          I.1     Isolate the affected   1 hour Required Action F.1              penetration flow and referenced in                path(s).
G.1 Isolate associated MSL.
Table 3.3.6.1-1.
OR G.2.1 Be in MODE 3.
(continued)
AND G.2.2 Be in MODE 4.
CLINTON                          3.3-50                        Amendment No. 95
12 hours 12 hours 36 hours H. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
H.1 Be in MODE 2.
6 hours I. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
I.1 Isolate the affected penetration flow path(s).
1 hour (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-51 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME J. As required by         J.1    Isolate the affected    24 hours Required Action F.1             penetration flow and referenced in               path(s).
CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
Table 3.3.6.1-1.
J.1 Isolate the affected penetration flow path(s).
K. As required by         K.1    Be in MODE 3.          12 hours Required Action F.1 and referenced in       AND Table 3.3.6.1-1.
24 hours K. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
K.2    Be in MODE 4.          36 hours OR Required Action and associated Completion Time of Condition I or J not met.
OR Required Action and associated Completion Time of Condition I or J not met.
L. As required by         L.1    Declare associated      1 hour Required Action F.1             standby liquid and referenced in               control subsystem Table 3.3.6.1-1.               inoperable.
K.1 Be in MODE 3.
OR L.2     Isolate the Reactor     1 hour Water Cleanup System.
AND K.2 Be in MODE 4.
M. As required by         M.1    Initiate action to      Immediately Required Action F.1             restore channel to and referenced in               OPERABLE status.
12 hours 36 hours L. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
Table 3.3.6.1-1.
L.1 Declare associated standby liquid control subsystem inoperable.
OR M.2     Initiate action to     Immediately isolate the Residual Heat Removal (RHR)
OR L.2 Isolate the Reactor Water Cleanup System.
1 hour 1 hour M. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
M.1 Initiate action to restore channel to OPERABLE status.
OR M.2 Initiate action to isolate the Residual Heat Removal (RHR)
Shutdown Cooling System suction from the reactor vessel.
Shutdown Cooling System suction from the reactor vessel.
OR (continued)
OR Immediately Immediately (continued)  
CLINTON                          3.3-51                        Amendment No. 95


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION                     REQUIRED ACTION         COMPLETION TIME M.     (Continued)             M.3.1     Initiate action to       Immediately restore secondary containment to OPERABLE status.
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-52 Amendment No. 95 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M.
AND M.3.2     Initiate action to       Immediately restore one standby gas treatment (SGT) subsystem to OPERABLE status.
(Continued)
AND M.3.3     Initiate action to       Immediately restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.
M.3.1 Initiate action to restore secondary containment to OPERABLE status.
AND M.3.4     ---------NOTE-------
AND M.3.2 Initiate action to restore one standby gas treatment (SGT) subsystem to OPERABLE status.
AND M.3.3 Initiate action to restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.
AND M.3.4  
---------NOTE-------
Entry and exit is permissible under administrative control.
Entry and exit is permissible under administrative control.
Initiate action to close one door in the upper containment personnel   Immediately air lock.
Initiate action to close one door in the upper containment personnel air lock.
N. As required by         N.1      Isolate the affected    Immediately Required Action F.1               penetration flow and referenced in                 path(s).
Immediately Immediately Immediately Immediately N.
Table 3.3.6.1-1.
As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
OR N.2       Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
N.1 Isolate the affected penetration flow path(s).
AND N.2.2     Initiate action to       Immediately suspend operations with a potential for draining the reactor vessel.
OR N.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
(continued)
AND N.2.2 Initiate action to suspend operations with a potential for draining the reactor vessel.
CLINTON                            3.3-52                          Amendment No. 95
Immediately Immediately Immediately (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CONDITION                   REQUIRED ACTION         COMPLETION TIME O. As required by         O.1    Isolate the affected    Immediately Required Action F.1           penetration flow and referenced in             path(s).
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-53 Amendment No. 192 CONDITION REQUIRED ACTION COMPLETION TIME O.
Table 3.3.6.1-1.
As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
OR O.2     Initiate action to     Immediately suspend operations with a potential for draining the reactor vessel.
O.1 Isolate the affected penetration flow path(s).
SURVEILLANCE REQUIREMENTS
OR O.2 Initiate action to suspend operations with a potential for draining the reactor vessel.
Immediately Immediately SURVEILLANCE REQUIREMENTS  
------------------------------------NOTES------------------------------------
------------------------------------NOTES------------------------------------
: 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
: 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours, provided the associated Function maintains isolation capability.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours, provided the associated Function maintains isolation capability.
SURVEILLANCE                             FREQUENCY SR 3.3.6.1.1     Perform CHANNEL CHECK.                     In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2     Perform CHANNEL FUNCTIONAL TEST.           In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3     Calibrate the analog trip module.         In accordance with the Surveillance Frequency Control Program (continued)
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.
CLINTON                          3.3-53                      Amendment No. 192
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Calibrate the analog trip module.
In accordance with the Surveillance Frequency Control Program (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-54 Amendment No. 192 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                             FREQUENCY SR 3.3.6.1.4     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6     Perform LOGIC SYSTEM FUNCTIONAL TEST.     In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7     ---------------NOTE---------------------
SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7  
---------------NOTE---------------------
Channel sensors are excluded.
Channel sensors are excluded.
Verify the ISOLATION SYSTEM RESPONSE       In accordance TIME for the main steam isolation valves   with the is within limits.                         Surveillance Frequency Control Program SR 3.3.6.1.8     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-54                      Amendment No. 192
Verify the ISOLATION SYSTEM RESPONSE TIME for the main steam isolation valves is within limits.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-55 Amendment No. 169 Table 3.3.6.1-1 (page 1 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1   REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Main Steam Line Isolation
: 1. Main Steam Line Isolation
: a. Reactor Vessel Water         1,2,3         4         G     SR 3.3.6.1.1   -148.1 inches Level-Low Low Low,                                            SR 3.3.6.1.2 Level 1                                                      SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4
: b. Main Steam Line                 1           4         H     SR 3.3.6.1.1   841 psig Pressure-Low                                                  SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8  
: c. Main Steam Line               1,2,3         4         G       SR 3.3.6.1.1   284 psid Flow-High                                                    SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
-148.1 inches
: d. Condenser Vacuum-Low         1,2(a),       4         G     SR 3.3.6.1.1   7.6 inches SR 3.3.6.1.2 Hg vacuum 3(a)                          SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. Main Steam Line Pressure-Low 1
: e. Main Steam Tunnel             1,2,3         4         G       SR 3.3.6.1.1   171&deg;F Temperature-High                                              SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
4 H
: f. Main Steam Line Turbine       1,2,3         4         G       SR 3.3.6.1.1 Modules 1-4 Building                                                      SR 3.3.6.1.2   142&deg;F, Temperature-High                                              SR 3.3.6.1.5  Module 5 SR 3.3.6.1.6   150&deg;F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 841 psig
: g. Manual Initiation             1,2,3         4         J       SR 3.3.6.1.6 NA (continued)
: c. Main Steam Line Flow-High 1,2,3 4
(a) With any turbine stop valve not closed.
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 284 psid
CLINTON                                    3.3-55                            Amendment No. 169
: d. Condenser Vacuum-Low 1,2(a),
3(a) 4 G
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7.6 inches Hg vacuum
: e. Main Steam Tunnel Temperature-High 1,2,3 4
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: f. Main Steam Line Turbine Building Temperature-High 1,2,3 4
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 Modules 1-4 142&deg;F, Module 5 150&deg;F
: g. Manual Initiation 1,2,3 4
J SR 3.3.6.1.6 NA (continued)
(a) With any turbine stop valve not closed.  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-56 Amendment No. 169 Table 3.3.6.1-1 (page 2 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. Primary Containment and Drywell Isolation
: 2. Primary Containment and Drywell Isolation
: a. Reactor Vessel Water       1,2,3         4(b)       K     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level 2                                      SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 (c) 4          O    SR 3.3.6.1.1   -48.1 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8
: a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 (c) 4(b) 4 K
: b. Drywell Pressure-High       1,2,3         4(b)       K     SR 3.3.6.1.1   1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
O SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
-48.1 inches
: b. Drywell Pressure-High 1,2,3 4(b)
K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: c. Deleted
: c. Deleted
: d. Drywell Pressure-High       1,2,3         4(b)       I     SR 3.3.6.1.1   1.88 psig (ECCS Divisions 1                                          SR 3.3.6.1.2 and 2)                                                      SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: d. Drywell Pressure-High (ECCS Divisions 1 and 2) 1,2,3 4(b)
: e. Reactor Vessel Water       1,2,3         4         I     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level                                        SR 3.3.6.1.2 2 (HPCS NSPS Div 3                                          SR 3.3.6.1.3 and 4)                                                      SR 3.3.6.1.6 SR 3.3.6.1.8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: f. Drywell Pressure-High       1,2,3         4         I     SR 3.3.6.1.1   1.88 psig (HPCS NSPS Div 3 and                                        SR 3.3.6.1.2
: e. Reactor Vessel Water Level-Low Low, Level 2 (HPCS NSPS Div 3 and 4) 1,2,3 4
: 4)                                                          SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
: f. Drywell Pressure-High (HPCS NSPS Div 3 and
: 4) 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig (continued)
(b) Also required to initiate the associated drywell isolation function.
(b) Also required to initiate the associated drywell isolation function.
(c) During operations with a potential for draining the reactor vessel.
(c) During operations with a potential for draining the reactor vessel.  
CLINTON                                    3.3-56                            Amendment No. 169


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-57 Amendment No. 169 Table 3.3.6.1-1 (page 3 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE                   CONDITIONS MODES OR       REQUIRED   REFERENCED OTHER        CHANNELS     FROM SPECIFIED          PER     REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS       FUNCTION  ACTION F.1   REQUIREMENTS     VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. Primary Containment and Drywell Isolation (continued)
: 2. Primary Containment and Drywell Isolation (continued)
: g. Containment Building       (c),(dc) 4         N     SR   3.3.6.1.1 500 mR/hr Fuel Transfer Pool                                                SR 3.3.6.1.2 Ventilation Plenum                                                SR 3.3.6.1.5 Radiation-High                                                    SR 3.3.6.1.6
: g. Containment Building Fuel Transfer Pool Ventilation Plenum Radiation-High (c),(dc) 4 N
: h. Containment Building       1,2,3           4(b)         I     SR   3.3.6.1.1 400 mR/hr Exhaust                                                          SR 3.3.6.1.2 Radiation-High                                                    SR 3.3.6.1.5 SR 3.3.6.1.6 (c),(dc) 4         N     SR   3.3.6.1.1 400 mR/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 500 mR/hr
: i. Containment Building       1,2,3           4(b)         I     SR   3.3.6.1.1 400 mR/hr Continuous                                                        SR 3.3.6.1.2 Containment Purge                                                SR 3.3.6.1.5 (CCP) Exhaust                                                    SR 3.3.6.1.6 Radiation-High (c),(dc) 4         N     SR   3.3.6.1.1 400 mR/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
: h. Containment Building Exhaust Radiation-High 1,2,3 4(b)
: j. Reactor Vessel Water       1,2,3           4(b)         I     SR   3.3.6.1.1 -148.1 inches Level-Low Low Low,                                                SR 3.3.6.1.2 Level 1                                                          SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 (c) 4         O       SR 3.3.6.1.1   -148.1 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.86 (ed)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c),(dc) 4 N
: k. Containment Pressure-                         2         I     SR   3.3.6.1.1 3.0 psid High                                                              SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr
: l. Manual Initiation           1,2,3           2(b)         J     SR   3.3.6.1.6 NA (c)(dc) 2         N     SR   3.3.6.1.6 NA (continued)
: i. Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3 4(b)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c),(dc) 4 N
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr
: j. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4(b)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-148.1 inches (c) 4 O
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.86  
-148.1 inches
: k. Containment Pressure-High (ed) 2 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 3.0 psid
: l. Manual Initiation 1,2,3 2(b)
J SR 3.3.6.1.6 NA (c)(dc) 2 N
SR 3.3.6.1.6 NA (continued)
(b) Also required to initiate the associated drywell isolation function.
(b) Also required to initiate the associated drywell isolation function.
(c) During operations with a potential for draining the reactor vessel.
(c) During operations with a potential for draining the reactor vessel.
(dc) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(dc) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(ed) MODES 1, 2, and 3 with the associated PCIVs not closed.
(ed) MODES 1, 2, and 3 with the associated PCIVs not closed.  
CLINTON                                      3.3-57                            Amendment No. 169


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-58 Amendment No. 169 Table 3.3.6.1-1 (page 4 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED  SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. Reactor Core Isolation Cooling (RCIC) System Isolation
: 3. Reactor Core Isolation Cooling (RCIC) System Isolation
: a. Auxiliary Building           1,2,3         2         I     SR 3.3.6.1.1   118.5 inches RCIC Steam Line                                            SR 3.3.6.1.2 water Flow-High                                                  SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: a. Auxiliary Building RCIC Steam Line Flow-High 1,2,3 2
: b. RCIC Steam Line             1,2,3         2         I     SR 3.3.6.1.2   13 seconds Flow-High,                                                  SR 3.3.6.1.5 Time Delay                                                  SR 3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 118.5 inches water
: c. RCIC Steam Supply Line       1,2,3         2         I     SR 3.3.6.1.1   52 psig Pressure-Low                                                SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. RCIC Steam Line Flow-High, Time Delay 1,2,3 2
: d. RCIC Turbine Exhaust         1,2,3         4         I     SR 3.3.6.1.1   20 psig Diaphragm                                                  SR 3.3.6.1.2 Pressure-High                                              SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 13 seconds
: e. RCIC Equipment Room         1,2,3         2         I     SR 3.3.6.1.1   207&deg;F Ambient                                                    SR 3.3.6.1.2 Temperature-High                                            SR 3.3.6.1.5 SR 3.3.6.1.6
: c. RCIC Steam Supply Line Pressure-Low 1,2,3 2
: f. Main Steam Line Tunnel       1,2,3         2         I     SR   3.3.6.1.1 171&deg;F Ambient                                                    SR   3.3.6.1.2 Temperature-High                                            SR   3.3.6.1.5 SR   3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 52 psig
: g. Main Steam Line Tunnel       1,2,3         2         I     SR 3.3.6.1.2   28 minutes Temperature Timer                                          SR   3.3.6.1.5 SR   3.3.6.1.6
: d. RCIC Turbine Exhaust Diaphragm Pressure-High 1,2,3 4
: h. Reactor Vessel Water         1,2,3         4         I     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level 2                                      SR   3.3.6.1.2 SR   3.3.6.1.3 SR   3.3.6.1.6 SR   3.3.6.1.8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 20 psig
: i. Drywell RCIC Steam           1,2,3         2         I     SR 3.3.6.1.1   188 inches Line Flow - High                                            SR   3.3.6.1.2 water SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6 (continued)
: e. RCIC Equipment Room Ambient Temperature-High 1,2,3 2
CLINTON                                    3.3-58                            Amendment No. 169
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 207&deg;F
: f. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: g. Main Steam Line Tunnel Temperature Timer 1,2,3 2
I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 28 minutes
: h. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
: i. Drywell RCIC Steam Line Flow - High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188 inches water (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-59 Amendment No. 169 Table 3.3.6.1-1 (page 5 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR     REQUIRED REFERENCED OTHER      CHANNELS   FROM SPECIFIED        PER   REQUIRED  SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS     FUNCTION ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. RCIC System Isolation (continued)
: 3.
: j. Drywell Pressure - High       1,2,3         2         I     SR   3.3.6.1.1 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
RCIC System Isolation (continued)
: k. Manual Initiation             1,2,3         1         J     SR   3.3.6.1.6 NA
: j. Drywell Pressure - High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: k. Manual Initiation 1,2,3 1
J SR 3.3.6.1.6 NA
: 4. Reactor Water Cleanup (RWCU) System Isolation
: 4. Reactor Water Cleanup (RWCU) System Isolation
: a. Differential Flow -           1,2,3         2         I     SR   3.3.6.1.1 66.1 gpm High                                                          SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8
: a. Differential Flow -
: b. Differential Flow-Timer       1,2,3         2         I     SR   3.3.6.1.2 47 seconds SR 3.3.6.1.4 SR 3.3.6.1.6
High 1,2,3 2
: c. RWCU Heat Exchanger           1,2,3       2 per       I     SR   3.3.6.1.1 205&deg;F Equipment Room                              room              SR 3.3.6.1.2 Temperature-High                                              SR 3.3.6.1.5 SR 3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8 66.1 gpm
: d. RWCU Pump Rooms               1,2,3       2 per       I     SR   3.3.6.1.1 202&deg;F Temperature-High                            room              SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. Differential Flow-Timer 1,2,3 2
: e. Main Steam Line Tunnel       1,2,3         2         I     SR   3.3.6.1.1 171&deg;F Ambient Temperature-                                          SR 3.3.6.1.2 High                                                          SR 3.3.6.1.5 SR 3.3.6.1.6
I SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 47 seconds
: f. Reactor Vessel Water         1,2,3         4         I     SR   3.3.6.1.1 -48.1 inches Level-Low Low,                                                SR 3.3.6.1.2 Level 2                                                      SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 (c) 4       O     SR 3.3.6.1.1 -48.1 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.68
: c. RWCU Heat Exchanger Equipment Room Temperature-High 1,2,3 2 per room I
: g. Standby Liquid Control       1,2,3         2         L     SR   3.3.6.1.6 NA System Initiation
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 205&deg;F
: h. Manual Initiation             1,2,3           2       J     SR 3.3.6.1.6 NA (c),(dc) 2        N      SR 3.3.6.1.6 NA (continued)
: d. RWCU Pump Rooms Temperature-High 1,2,3 2 per room I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 202&deg;F
: e. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: f. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches (c) 4 O
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.68  
-48.1 inches
: g. Standby Liquid Control System Initiation 1,2,3 2
L SR 3.3.6.1.6 NA
: h. Manual Initiation 1,2,3 (c),(dc) 2 2
J N
SR 3.3.6.1.6 SR 3.3.6.1.6 NA NA (continued)
(c) During operations with a potential for draining the reactor vessel.
(c) During operations with a potential for draining the reactor vessel.
(dc)     During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(dc)
CLINTON                                      3.3-59                          Amendment No. 169
During movement of recently irradiated fuel assemblies in the primary or secondary containment.  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-60 Amendment No. 169 Table 3.3.6.1-1 (page 6 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER       REQUIRED       FROM SPECIFIED    CHANNELS PER   REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION           CONDITIONS     FUNCTION    ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. RHR System Isolation
: 5. RHR System Isolation
: a. RHR Heat Exchanger         1,2,3     2 per room       I     SR 3.3.6.1.1   160&deg;F Ambient                                                        SR 3.3.6.1.2 Temperature-High                                              SR 3.3.6.1.5 SR 3.3.6.1.6
: a. RHR Heat Exchanger Ambient Temperature-High 1,2,3 2 per room I
: b. Reactor Vessel Water     1,2,3(fe)         4           I     SR 3.3.6.1.1   8.3 inches Level - Low, Level 3                                          SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 160&deg;F
: c. Reactor Vessel Water     3(gf),4,5       4(h)         M     SR 3.3.6.1.1   8.3 inches Level - Low, Level 3                                          SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. Reactor Vessel Water Level - Low, Level 3 1,2,3(fe) 4 I
: d. Reactor Vessel Water       1,2,3           4           I     SR 3.3.6.1.1   -148.1 Level - Low Low Low,                                          SR 3.3.6.1.2 inches Level 1                                                        SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches
: e. Reactor Vessel             1,2,3           4           I     SR 3.3.6.1.1   113 psig Pressure-High                                                  SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: c. Reactor Vessel Water Level - Low, Level 3 3(gf),4,5 4(h)
: f. Drywell Pressure-High     1,2,3           8           I     SR 3.3.6.1.1   1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
M SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches
: g. Manual Initiation         1,2,3           2           J     SR 3.3.6.1.6 NA (fe) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.
: d. Reactor Vessel Water Level - Low Low Low, Level 1 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-148.1 inches
: e. Reactor Vessel Pressure-High 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 113 psig
: f. Drywell Pressure-High 1,2,3 8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: g. Manual Initiation 1,2,3 2
J SR 3.3.6.1.6 NA (fe) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.
(gf) With reactor steam dome pressure less than the RHR cut in permissive pressure.
(gf) With reactor steam dome pressure less than the RHR cut in permissive pressure.
(h) Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.
(h) Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.  
CLINTON                                    3.3-60                            Amendment No. 169


Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation 3.3.6.2 CLINTON 3.3-64 Amendment No. 169 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation APPLICABLE MODES OR     REQUIRED OTHER      CHANNELS SPECIFIED      PER TRIP SURVEILLANCE         ALLOWABLE FUNCTION              CONDITIONS      SYSTEM  REQUIREMENTS          VALUE
Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Reactor Vessel Water         1,2,3,(a)         2   SR 3.3.6.2.1   -48.1 inches Level-Low Low, Level 2                                SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6
: 1.
: 2. Drywell Pressure-High           1,2,3         2     SR 3.3.6.2.1   1.88 psig SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 (a)
Reactor Vessel Water Level-Low Low, Level 2 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6  
: 3. Containment Building Fuel           ,(b)         2   SR 3.3.6.2.1   500 mR/hr Transfer Pool Ventilation                            SR 3.3.6.2.2 Plenum Exhaust                                        SR 3.3.6.2.4 Radiation-High                                        SR 3.3.6.2.5
-48.1 inches
: 4. Containment Building       1,2,3,(a),(b)       2   SR 3.3.6.2.1   400 mR/hr Exhaust Radiation-High                                SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5
: 2.
: 5. Containment Building           1,2,3, (a) 2   SR 3.3.6.2.1   400 mR/hr Continuous Containment              ,(b)              SR 3.3.6.2.2 Purge (CCP) Exhaust                                  SR 3.3.6.2.4 Radiation-High                                        SR 3.3.6.2.5
Drywell Pressure-High 1,2,3 2
: 6. Fuel Building Exhaust           1,2,3, (cb) 2   SR 3.3.6.2.1   17 mR/hr Radiation-High                                        SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5
SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 1.88 psig
: 7. Manual Initiation               1,2,3,           1   SR 3.3.6.2.5 NA (a)
: 3.
                                          ,(b)
Containment Building Fuel Transfer Pool Ventilation Plenum Exhaust Radiation-High (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 500 mR/hr
(a) During   operations with a potential for draining the reactor vessel.
: 4.
Containment Building Exhaust Radiation-High 1,2,3,(a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr
: 5.
Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3, (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr
: 6.
Fuel Building Exhaust Radiation-High 1,2,3, (cb) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 17 mR/hr
: 7.
Manual Initiation 1,2,3, (a),(b) 1 SR 3.3.6.2.5 NA (a) During operations with a potential for draining the reactor vessel.
(ba) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(ba) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(cb) During movement of recently irradiated fuel assemblies in the fuel building.
(cb) During movement of recently irradiated fuel assemblies in the fuel building.  
CLINTON                                      3.3-64                        Amendment No. 169


Control Room Ventilation System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)
Control Room Ventilation System Instrumentation 3.3.7.1 CLINTON 3.3-77 Amendment No. 152 Table 3.3.7.1-1 (page 1 of 1)
Control Room Ventilation System Instrumentation APPLICABLE MODES OR OTHER         REQUIRED SPECIFIED        CHANNELS PER   SURVEILLANCE        ALLOWABLE FUNCTION        CONDITIONS        TRIP SYSTEM   REQUIREMENTS         VALUE
Control Room Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Control           1,2,3, (a) 1/Intake   SR 3.3.7.1.1   26 mR/hr Room Air              ,(b)                      SR 3.3.7.1.2 Intake                                          SR 3.3.7.1.3 Radiation Monitors (a) During operations with a potential for draining the reactor vessel.
: 1. Control Room Air Intake Radiation Monitors 1,2,3, (a),(b) 1/Intake SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 26 mR/hr (a) During operations with a potential for draining the reactor vessel.
(ba) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.
(ba) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.  
CLINTON                                    3.3-77                            Amendment No. 152


ECCS Operating 3.5.1 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
ECCS Operating 3.5.1 CLINTON 3.5-1 Amendment No. 163 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.1   ECCS Operating LCO 3.5.1         Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/
SYSTEM 3.5.1 ECCS Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/
relief valves shall be OPERABLE.
relief valves shall be OPERABLE.  
                  ----------------------------NOTE----------------------------
----------------------------NOTE----------------------------
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
APPLICABILITY:     MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.4.b is not applicable to HPCS.
LCO 3.0.4.b is not applicable to HPCS.
CONDITION                   REQUIRED ACTION         COMPLETION TIME A. One low pressure ECCS     A.1     Restore low pressure   7 days injection/spray                    ECCS injection/spray subsystem inoperable.              subsystem to OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.
B. High Pressure Core       B.1     Verify by             1 hour Spray (HPCS) System                administrative means inoperable.                        RCIC System is OPERABLE when RCIC is required to be OPERABLE.
A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.
AND B.2     Restore HPCS System   14 days to OPERABLE status.
7 days B. High Pressure Core Spray (HPCS) System inoperable.
(continued)
B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.
CLINTON                                3.5-1                  Amendment No. 163
AND B.2 Restore HPCS System to OPERABLE status.
1 hour 14 days (continued)  


ECCS ShutdownRPV Water Inventory Control 3.5.2 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2   ECCS   ShutdownRPV Water Inventory Control LCO 3.5.2           DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-6 Amendment No. 133 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS  ShutdownRPV Water Inventory Control LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
AND Two One ECCS injection/spray subsystems shall be OPERABLE.
AND Two One ECCS injection/spray subsystems shall be OPERABLE.  
                    ----------------------------NOTE----------------------------One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
----------------------------NOTE----------------------------One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
APPLICABILITY:       MODES 4 and, MODE 5 except with the reactor cavity to steam dryer pool gate removed and water level   22 ft 8 inches over the top of the reactor pressure vessel flange.
APPLICABILITY:
ACTIONS CONDITION                     REQUIRED ACTION             COMPLETION TIME A. ROne required ECCS           A.1     Restore required ECCS     4 hours injection/spray                      injection/spray subsystem inoperable.                subsystem to OPERABLE status.
MODES 4 and, MODE 5 except with the reactor cavity to steam dryer pool gate removed and water level  22 ft 8 inches over the top of the reactor pressure vessel flange.
B. Required Action and         B.1     Initiate action to         Immediately associated Completion                establish a method of Time of Condition A not              water injection capable met.                                  of operating without offsite electrical power.suspend operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
C. Two required ECCS           C.1     Initiate action to         Immediately injection/spray                      suspend OPDRVs.
ROne required ECCS injection/spray subsystem inoperable.
subsystems inoperable.
A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.
AND C.2     Restore one ECCS           4 hours injection/spray subsystem to OPERABLE status.
4 hours B.
(continued)
Required Action and associated Completion Time of Condition A not met.
CLINTON                                    3.5-6                      Amendment No. 133
B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.suspend operations with a potential for draining the reactor vessel (OPDRVs).
Immediately C.
Two required ECCS injection/spray subsystems inoperable.
C.1 Initiate action to suspend OPDRVs.
AND C.2 Restore one ECCS injection/spray subsystem to OPERABLE status.
Immediately 4 hours (continued)  


ECCS ShutdownRPV Water Inventory Control 3.5.2 ACTIONS (continued)
ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-7 Amendment No. 133 ACTIONS (continued)
CONDITION           REQUIRED ACTION         COMPLETION TIME C. DRAIN TIME < 36 hours C.1 Verify secondary         4 hours and  8 hours.            containment boundary is capable of being established in less than the DRAIN TIME.
CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours and 8 hours.
AND C.2 Verify each secondary     4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
C.1 Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.
AND C.3 Verify one standby gas   4 hours treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
(continued)
AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
CLINTON                        3.5-7                    Amendment No. 133
4 hours 4 hours 4 hours (continued)


ECCS ShutdownRPV Water Inventory Control 3.5.2 ACTIONS (continued)
ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-8 Amendment No. 133 ACTIONS (continued)
CONDITION                     REQUIRED ACTION           COMPLETION TIME D. DRAIN TIME < 8           D.1       ------- NOTE --------
CONDITION REQUIRED ACTION COMPLETION TIME D.
hours.Required Action C.2          Required ECCS and associated Completion          injection/spray subsystem Time not met.                      or additional method of water injection shall be capable of operating without offsite electrical power.
DRAIN TIME < 8 hours.Required Action C.2 and associated Completion Time not met.
Initiate action to establish an additional method of water injection Immediately with water sources capable of maintaining RPV water level > TAF for 36 hours.
D.1  
AND D.2       Initiate action to restore establish secondary containment to OPERABLE statusboundary. Immediately AND D.23     Initiate action to isolate each secondary containment penetration flow path or verify it   Immediately can be manually isolated from the control room.
------- NOTE --------
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.
AND D.2 Initiate action to restore establish secondary containment to OPERABLE statusboundary.
AND D.23 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
Initiate action to restore one standby gas treatment subsystem to OPERABLE status.
Initiate action to restore one standby gas treatment subsystem to OPERABLE status.
AND D.34     Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
AND D.34 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
Immediately AND D.4       --------NOTE--------
AND D.4  
--------NOTE--------
Entry and exit is permissible under administrative control.
Entry and exit is permissible under administrative control.
Initiate action to close one door in the upper containment personnel air lock.
Initiate action to close one door in the upper containment personnel air lock.
(continued)
Immediately Immediately Immediately Immediately (continued)  
CLINTON                                  3.5-8                      Amendment No. 133


ECCS ShutdownRPV Water Inventory Control 3.5.2 ACTIONS (continued)
ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-9 Amendment No. 204 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME E. Required Action and     E.1      Initiate action to      Immediately associated Completion             restore DRAIN TIME to Time of Condition C               36 hours.
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.
or D not met.
OR DRAIN TIME < 1 hour.
OR DRAIN TIME < 1 hour.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.5.2.1   Verify DRAIN TIME 36 hours.                   In accordance with the Surveillance Frequency Control Program SR 3.5.2.12   Verify, for each a required low pressure       In accordance ECCS injection/spray subsystem, the            with the suppression pool water level is 12 ft 8       Surveillance inches.                                         Frequency Control Program SR 3.5.2.23   Verify, for the a required High Pressure       In accordance Core Spray (HPCS) System, the:                 with the Surveillance
E.1 Initiate action to restore DRAIN TIME to 36 hours.
: a. Suppression pool water level is           Frequency 12 ft 8 inches; or                       Control Program
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours.
: b. RCIC storage tank available water volume is 125,000 gal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.12 Verify, for each a required low pressure ECCS injection/spray subsystem, the suppression pool water level is 12 ft 8 inches.
SR 3.5.2.34   Verify, for each the required ECCS             In accordance injection/spray subsystem, locations           with the susceptible to gas accumulation are             Surveillance sufficiently filled with water.                 Frequency Control Program (continued)
In accordance with the Surveillance Frequency Control Program SR 3.5.2.23 Verify, for the a required High Pressure Core Spray (HPCS) System, the:
CLINTON                              3.5-9                    Amendment No. 204
: a.
Suppression pool water level is 12 ft 8 inches; or
: b.
RCIC storage tank available water volume is 125,000 gal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.34 Verify, for each the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program (continued)  


ECCS ShutdownRPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS   (continued)
ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-10 Amendment No. 204 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                             FREQUENCY SR 3.5.2.45   ---------------------NOTES-----------------
SURVEILLANCE FREQUENCY SR 3.5.2.45  
---------------------NOTES-----------------
: 1. One low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.
: 1. One low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.
: 2. Not required to be met for system vent flow paths opened under administrative control.
: 2. Not required to be met for system vent flow paths opened under administrative control.
Verify, each for the required ECCS             In accordance injection/spray subsystem, each manual,         with the power operated, and automatic valve in the     Surveillance flow path, that is not locked, sealed, or       Frequency otherwise secured in position, is in the       Control Program correct position.
Verify, each for the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.56   Operate the required ECCS injection/spray       In accordance subsystem through the recirculation line       with the for 10 minutes.Verify each required ECCS     Surveillance pump develops the specified flow rate with     Frequency the specified pump differential pressure.       Control Program PUMP DIFFERENTIAL SYSTEM       FLOW RATE           PRESSURE LPCS         5010 gpm         290 psid LPCI         5050 gpm         113 psid HPCS         5010 gpm         363 psid SR 3.5.2.7     Verify each valve credited for                 In accordance automatically isolating a penetration flow     with the path actuates to the isolation position on     Surveillance an actual or simulated isolation signal.       Frequency Control Program SR 3.5.2.68   -------------------NOTE--------------------
In accordance with the Surveillance Frequency Control Program SR 3.5.2.56 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.Verify each required ECCS pump develops the specified flow rate with the specified pump differential pressure.
PUMP DIFFERENTIAL SYSTEM FLOW RATE PRESSURE LPCS 5010 gpm 290 psid LPCI 5050 gpm 113 psid HPCS 5010 gpm 363 psid In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.68  
-------------------NOTE--------------------
Vessel injection/spray may be excluded.
Vessel injection/spray may be excluded.
Verify each the required ECCS                   In Accordance injection/spray subsystem can be manually       with the operated.actuates on an actual or simulated     Surveillance automatic initiation signal.                   Frequency Control Program CLINTON                              3.5-10                    Amendment No. 204
Verify each the required ECCS injection/spray subsystem can be manually operated.actuates on an actual or simulated automatic initiation signal.
In Accordance with the Surveillance Frequency Control Program  


RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
RCIC System 3.5.3 CLINTON 3.5-11 Amendment No. XXX 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.3   RCIC System LCO 3.5.3       The RCIC System shall be OPERABLE.
SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.
APPLICABILITY:   MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.4.b is not applicable to RCIC.
LCO 3.0.4.b is not applicable to RCIC.
CONDITION                   REQUIRED ACTION       COMPLETION TIME A. RCIC System               A.1     Verify by             1 hour inoperable.                        administrative means High Pressure Core Spray System is OPERABLE.
CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.
AND A.2     Restore RCIC System   14 days to OPERABLE status.
A.1 Verify by administrative means High Pressure Core Spray System is OPERABLE.
B. Required Action and       B.1     Be in MODE 3.         12 hours associated Completion Time not met.            AND B.2     Reduce reactor steam 36 hours dome pressure to 150 psig.
AND A.2 Restore RCIC System to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                           FREQUENCY SR 3.5.3.1     Verify the RCIC System locations             In accordance susceptible to gas accumulation are           with the sufficiently filled with water.               Surveillance Frequency Control Program (continued)
1 hour 14 days B. Required Action and associated Completion Time not met.
CLINTON                              3.5-11                  Amendment No. XXX
B.1 Be in MODE 3.
AND B.2 Reduce reactor steam dome pressure to 150 psig.
12 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program (continued)  


RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS   (continued)
RCIC System 3.5.3 CLINTON 3.5-12 Amendment No. XXX SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                           FREQUENCY SR 3.5.3.2   -------------------NOTE--------------------
SURVEILLANCE FREQUENCY SR 3.5.3.2  
-------------------NOTE--------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify each RCIC System manual, power       In accordance operated, and automatic valve in the flow   with the path, that is not locked, sealed, or         Surveillance otherwise secured in position, is in the     Frequency correct position.                           Control Program SR 3.5.3.3   -------------------NOTE--------------------
Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.3  
-------------------NOTE--------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with RCIC steam supply pressure     In accordance 1045 psig and 920 psig, the RCIC pump   with the can develop a flow rate 600 gpm against a Surveillance system head corresponding to reactor         Frequency pressure.                                   Control Program SR 3.5.3.4   -------------------NOTE--------------------
Verify, with RCIC steam supply pressure 1045 psig and 920 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.4  
-------------------NOTE--------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with RCIC steam supply pressure     In accordance 150 psig and 135 psig, the RCIC pump     with the can develop a flow rate 600 gpm against a Surveillance system head corresponding to reactor         Frequency pressure.                                   Control Program SR 3.5.3.5   -------------------NOTE--------------------
Verify, with RCIC steam supply pressure 150 psig and 135 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.5  
-------------------NOTE--------------------
Vessel injection may be excluded.
Vessel injection may be excluded.
Verify the RCIC System actuates on an       In accordance actual or simulated automatic initiation     with the signal.                                      Surveillance Frequency Control Program CLINTON                              3.5-12                Amendment No. XXX
Verify the RCIC System actuates on an actual or simulated automatic initiation signal.
In accordance with the Surveillance Frequency Control Program  


Primary Containment Air Locks 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2     Each primary containment air lock shall be OPERABLE.
Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-3 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 Each primary containment air lock shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3,
APPLICABILITY:
                -----------------------NOTE------------------------------
MODES 1, 2, and 3,  
-----------------------NOTE------------------------------
The following Applicabilityies appliesy only to the upper containment personnel air lock.
The following Applicabilityies appliesy only to the upper containment personnel air lock.
During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Entry and exit is permissible to perform repairs of the affected air lock components.
: 1. Entry and exit is permissible to perform repairs of the affected air lock components.
: 2. Separate Condition entry is allowed for each air lock.
: 2. Separate Condition entry is allowed for each air lock.
: 3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
(continued)
(continued)  
CLINTON                          3.6-3                      Amendment No. 147


Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)
Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-7 Amendment No. 147 ACTIONS (continued)
CONDITION               REQUIRED ACTION         COMPLETION TIME E. Required Action and     ------------NOTE------------
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition A, B, or C not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or OPDRVs.
associated Completion  LCO 3.0.3 is not applicable.
------------NOTE------------
Time of Condition A,  ----------------------------
LCO 3.0.3 is not applicable.
B, or C not met during movement of recently  E.1   Suspend movement of       Immediately irradiated fuel              recently irradiated assemblies in the            fuel assemblies in the primary or secondary        primary and secondary containment, or              containment.
E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
OPDRVs.
AND E.2 Initiation action to suspend OPDRVs.
AND E.2   Initiation action to     Immediately suspend OPDRVs.
Immediately Immediately
CLINTON                        3.6-7                      Amendment No. 147


PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
PCIVs 3.6.1.3 CLINTON 3.6-9 Amendment No. 158 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
LCO 3.6.1.3     Each PCIV shall be OPERABLE.
LCO 3.6.1.3 Each PCIV shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, MODES 4 and 5 for RHR Shutdown Cooling System suction from the reactor vessel isolation valves when associated isolation instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment and Drywell Isolation Instrumentation," Function 5.c.
APPLICABILITY:
                -----------------------NOTE------------------------------
MODES 1, 2, and 3, MODES 4 and 5 for RHR Shutdown Cooling System suction from the reactor vessel isolation valves when associated isolation instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment and Drywell Isolation Instrumentation," Function 5.c.  
-----------------------NOTE------------------------------
The following Applicabilityies apply applies only to secondary containment bypass leakage isolation valves.
The following Applicabilityies apply applies only to secondary containment bypass leakage isolation valves.
During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
Line 697: Line 918:
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
: 4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.
: 5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.
(continued)
(continued)  
CLINTON                          3.6-9                      Amendment No. 158


PCIVs 3.6.1.3 ACTIONS CONDITION                 REQUIRED ACTION     COMPLETION TIME D. (continued)           D.3   Perform SR 3.6.1.3.5 Once per 92 for the resilient     days seal purge valves closed to comply with Required Action D.1.
PCIVs 3.6.1.3 CLINTON 3.6-14 Amendment No. 147 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)
E. Required Action and   E.1    Be in MODE 3.        12 hours associated Completion Time of Condition A, AND B, C, or D not met in MODE 1, 2, or 3.     E.2   Be in MODE 4.         36 hours F. Required Action and   F.1   --------NOTE---------
D.3 Perform SR 3.6.1.3.5 for the resilient seal purge valves closed to comply with Required Action D.1.
associated Completion        LCO 3.0.3 is not Time of Condition A,        applicable.
Once per 92 days E. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.
B, C, or D not met          ---------------------
E.1 Be in MODE 3.
for PCIV(s) required to be OPERABLE during        Suspend movement of  Immediately movement of recently         recently irradiated irradiated fuel              fuel assemblies in assemblies in the            primary and secondary primary or secondary        containment.
AND E.2 Be in MODE 4.
containment.
12 hours 36 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during movement of recently irradiated fuel assemblies in the primary or secondary containment.
G. Required Action and   G.1  Initiate action to    Immediately associated Completion       suspend OPDRVs.
F.1  
Time of Condition A, B, C, or D not met   OR for PCIV(s) required to be OPERABLE during G.2   Initiate action to     Immediately MODE 4 or 5 or during      restore valve(s) to OPDRVs.                    OPERABLE status.
--------NOTE---------
(continued)
LCO 3.0.3 is not applicable.
CLINTON                        3.6-14                  Amendment No. 147
Suspend movement of recently irradiated fuel assemblies in primary and secondary containment.
Immediately G. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during MODE 4 or 5 or during OPDRVs.
G.1 Initiate action to suspend OPDRVs.
OR G.2 Initiate action to restore valve(s) to OPERABLE status.
Immediately Immediately (continued)  


Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1     The secondary containment shall be OPERABLE.
Secondary Containment 3.6.4.1 CLINTON 3.6-43 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                   REQUIRED ACTION         COMPLETION TIME A. Secondary containment   A.1    Restore secondary      4 hours inoperable in MODE 1,           containment to 2, or 3.                       OPERABLE status.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
B. Required Action and     ------------NOTE------------
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
associated Completion  LCO 3.0.4.a is not Time of Condition A    applicable when entering not met.                MODE 3.
Secondary containment inoperable in MODE 1, 2, or 3.
B.1     Be in MODE 3.           12 hours (continued)
A.1 Restore secondary containment to OPERABLE status.
CLINTON                          3.6-43                      Amendment No. 187
4 hours B.
Required Action and associated Completion Time of Condition A not met.
------------NOTE------------
LCO 3.0.4.a is not applicable when entering MODE 3.
B.1 Be in MODE 3.
12 hours (continued)  


Secondary Containment 3.6.4.1 ACTIONS (continued)
Secondary Containment 3.6.4.1 CLINTON 3.6-44 Amendment No. 192 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME C. Secondary containment     C.1     --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.
inoperable during                LCO 3.0.3 is not movement of recently            applicable.
C.1  
irradiated fuel                  ---------------------
--------NOTE---------
assemblies in the primary or secondary            Suspend movement of     Immediately containment, or during          recently irradiated OPDRVs.                          fuel assemblies in the primary and secondary containment.
LCO 3.0.3 is not applicable.
AND C.2     Initiate action to     Immediately suspend OPDRVs.
Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.6.4.1.1   Verify secondary containment vacuum is       In accordance 0.25 inch of vacuum water gauge.           with the Surveillance Frequency Control Program SR 3.6.4.1.2   Verify all secondary containment             In accordance equipment hatches are closed and sealed. with the Surveillance Frequency Control Program (continued)
AND C.2 Initiate action to suspend OPDRVs.
CLINTON                          3.6-44                      Amendment No. 192
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.
In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.
In accordance with the Surveillance Frequency Control Program (continued)  


SCIDs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)
SCIDs 3.6.4.2 CLINTON 3.6-47 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)
LCO 3.6.4.2     Each SCID shall be OPERABLE.
LCO 3.6.4.2 Each SCID shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 2. Separate Condition entry is allowed for each penetration flow path.
: 2. Separate Condition entry is allowed for each penetration flow path.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.
(continued)
(continued)  
CLINTON                          3.6-47                      Amendment No. 147


SCIDs 3.6.4.2 ACTIONS (continued)
SCIDs 3.6.4.2 CLINTON 3.6-49 Amendment No. 147 ACTIONS (continued)
CONDITION                 REQUIRED ACTION       COMPLETION TIME D. Required Action and     D.1     --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.
associated Completion          LCO 3.0.3 is not Time of Condition A or        applicable.
D.1  
B not met during              ---------------------
--------NOTE---------
movement of recently irradiated fuel                Suspend movement of   Immediately assemblies in the              recently irradiated primary or secondary          fuel assemblies in the containment, or during        primary and secondary OPDRVs.                        containment.
LCO 3.0.3 is not applicable.
AND D.2     Initiate action to     Immediately suspend OPDRVs.
Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
CLINTON                        3.6-49                    Amendment No. 147
AND D.2 Initiate action to suspend OPDRVs.
Immediately Immediately


SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3     Two SGT subsystems shall be OPERABLE.
SGT System 3.6.4.3 CLINTON 3.6-51 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION         COMPLETION TIME A. One SGT subsystem       A.1   Restore SGT subsystem   7 days inoperable.                    to OPERABLE status.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
B. Required Action and     ------------NOTE------------
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.
associated Completion    LCO 3.0.4.a is not Time of Condition A      applicable when entering not met in MODE 1, 2,    MODE 3.
A.1 Restore SGT subsystem to OPERABLE status.
or 3.                    ----------------------------
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
B.1   Be in MODE 3.           12 hours (continued)
------------NOTE------------
CLINTON                          3.6-51                      Amendment No. 187
LCO 3.0.4.a is not applicable when entering MODE 3.
B.1 Be in MODE 3.
12 hours (continued)  


SGT System 3.6.4.3 ACTIONS (continued)
SGT System 3.6.4.3 CLINTON 3.6-52 Amendment No. 187 ACTIONS (continued)
CONDITION                 REQUIRED ACTION       COMPLETION TIME C. Required Action and     -------------NOTE------------
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.
associated Completion  LCO 3.0.3 is not applicable.
-------------NOTE------------
Time of Condition A    -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of recently    C.1     Place OPERABLE SGT     Immediately irradiated fuel                  subsystem in assemblies in the                operation.
C.1 Place OPERABLE SGT subsystem in operation.
primary or secondary containment, or during  OR OPDRVs.
OR C.2.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
C.2.1   Suspend movement of   Immediately recently irradiated fuel assemblies in the primary and secondary containment.
AND C.2.2 Initiate action to suspend OPDRVs.
AND C.2.2   Initiate action to     Immediately suspend OPDRVs.
Immediately Immediately Immediately D.
D. Two SGT subsystems   ------------NOTE------------
Two SGT subsystems inoperable in MODE 1, 2, or 3.
inoperable in MODE 1, LCO 3.0.4.a is not 2, or 3.              applicable when entering MODE 3.
------------NOTE------------
D.1     Be in MODE 3.         12 hours (continued)
LCO 3.0.4.a is not applicable when entering MODE 3.
CLINTON                          3.6-52                    Amendment No. 187
D.1 Be in MODE 3.
12 hours (continued)  


SGT System 3.6.4.3 ACTIONS (continued)
SGT System 3.6.4.3 CLINTON 3.6-53 Amendment No. 201 ACTIONS (continued)
CONDITION                   REQUIRED ACTION       COMPLETION TIME E. Two SGT subsystems       E.1    Suspend movement of    Immediately inoperable during               recently irradiated movement of recently             fuel assemblies in the irradiated fuel                 primary and secondary assemblies in the               containment.
CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.
primary or secondary containment, or during   AND OPDRVs.
E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
E.2     Initiate action to     Immediately suspend OPDRVs.
AND E.2 Initiate action to suspend OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                           FREQUENCY SR 3.6.4.3.1     Operate each SGT subsystem for           In accordance 15 continuous minutes with             with the heaters operating.                       Surveillance Frequency Control Program SR 3.6.4.3.2     Perform required SGT filter testing in   In accordance accordance with the Ventilation Filter   with the VFTP Testing Program (VFTP).
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes with heaters operating.
SR 3.6.4.3.3     Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal. with the Surveillance Frequency Control Program SR 3.6.4.3.4     Verify each SGT filter cooling bypass     In accordance damper can be opened and the fan         with the started.                                  Surveillance Frequency Control Program CLINTON                          3.6-53                    Amendment No. 201
In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling bypass damper can be opened and the fan started.
In accordance with the Surveillance Frequency Control Program  


Control Room Ventilation System 3.7.3 3.7 PLANT SYSTEM 3.7.3   Control Room Ventilation System LCO 3.7.3       Two Control Room Ventilation subsystems shall be OPERABLE.
Control Room Ventilation System 3.7.3 CLINTON 3.7-4 Amendment No. 95 3.7 PLANT SYSTEM 3.7.3 Control Room Ventilation System LCO 3.7.3 Two Control Room Ventilation subsystems shall be OPERABLE.  
                  --------------------------NOTE---------------------------
--------------------------NOTE---------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY:   MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION         COMPLETION TIME A. One Control Room         A.1     Restore Control Room   7 days Ventilation                      Ventilation subsystem subsystem inoperable              to OPERABLE status.
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
for reasons other than Condition C.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Control Room Ventilation subsystem inoperable for reasons other than Condition C.
B. Required Action and     ------------NOTE-------------
A.1 Restore Control Room Ventilation subsystem to OPERABLE status.
associated              LCO 3.0.4.a is not Completion Time of      applicable when entering Condition A not met    MODE 3.
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
in MODE 1, 2, or 3.    -----------------------------
------------NOTE-------------
B.1     Be in MODE 3.           12 hours C. One or more Control     C.1      Initiate action to      Immediately Room Ventilation                 implement mitigating subsystems inoperable           actions.
LCO 3.0.4.a is not applicable when entering MODE 3.
due to inoperable CRE   AND boundary in MODE 1, 2, or 3.               C.2     Verify mitigating       24 hours actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
B.1 Be in MODE 3.
AND C.3     Restore CRE boundary   90 days to OPERABLE status.
12 hours C. One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.
(continued)
C.1 Initiate action to implement mitigating actions.
CLINTON                              3.7-4                    Amendment No. 95
AND C.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND C.3 Restore CRE boundary to OPERABLE status.
Immediately 24 hours 90 days (continued)  


Control Room Ventilation System 3.7.3 ACTIONS   (continued)
Control Room Ventilation System 3.7.3 CLINTON 3.7-5 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME D. Required Action and   D.1      Be in MODE 3.          12 hours Associated Completion Time of Condition C not met in MODE 1, 2, AND or 3.
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and Associated Completion Time of Condition C not met in MODE 1, 2, or 3.
D.2     Be in MODE 4.           36 hours E. Required Action and   ------------NOTE-------------
D.1 Be in MODE 3.
associated Completion  LCO 3.0.3 is not applicable.
AND D.2 Be in MODE 4.
Time of Condition A    -----------------------------
12 hours 36 hours E. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
not met during movement of irradiated E.1     Place OPERABLE         Immediately fuel assemblies in the          Control Room primary or secondary            Ventilation subsystem containment, or during          in high radiation CORE ALTERATIONS, or            mode.
------------NOTE-------------
during OPDRVs.
LCO 3.0.3 is not applicable.
OR E.2.1   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
E.1 Place OPERABLE Control Room Ventilation subsystem in high radiation mode.
AND E.2.2   Suspend CORE           Immediately ALTERATIONS.
OR E.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND E.2.3   Initiate action to     Immediately suspend OPDRVs.
AND E.2.2 Suspend CORE ALTERATIONS.
F. Two Control Room       ------------NOTE-------------
AND E.2.3 Initiate action to suspend OPDRVs.
Ventilation subsystems LCO 3.0.4.a is not inoperable in MODE 1,  applicable when entering 2, or 3 for reasons    MODE 3.
Immediately Immediately Immediately Immediately F. Two Control Room Ventilation subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition C.
other than Condition  -----------------------------
------------NOTE-------------
C.
LCO 3.0.4.a is not applicable when entering MODE 3.
F.1     Be in MODE 3.           12 hours (continued)
F.1 Be in MODE 3.
CLINTON                            3.7-5                    Amendment No. 95
12 hours (continued)


Control Room Ventilation System 3.7.3 ACTIONS (continued)
Control Room Ventilation System 3.7.3 CLINTON 3.7-6 Amendment No. 95 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME G. Two Control Room         G.1      Suspend movement of    Immediately Ventilation subsystems           irradiated fuel inoperable during                 assemblies in the movement of irradiated           primary and secondary fuel assemblies in the           containment.
CONDITION REQUIRED ACTION COMPLETION TIME G. Two Control Room Ventilation subsystems inoperable during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
primary or secondary containment, or during   AND CORE ALTERATIONS, or during OPDRVs.          G.2      Suspend CORE            Immediately ALTERATIONS.
OR One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
OR AND One or more Control Room Ventilation         G.3      Initiate action to      Immediately subsystems inoperable             suspend OPDRVs.
G.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
AND G.2 Suspend CORE ALTERATIONS.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.7.3.1   Operate each Control Room Ventilation           In accordance subsystem with flow through the makeup         with the filter for 15 continuous minutes with the     Surveillance heaters operating.                             Frequency Control Program SR 3.7.3.2   Operate each Control Room Ventilation           In accordance subsystem with flow through the                with the recirculation filter for 15 minutes.         Surveillance Frequency Control Program (continued)
AND G.3 Initiate action to suspend OPDRVs.
CLINTON                              3.7-6                    Amendment No. 95
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each Control Room Ventilation subsystem with flow through the makeup filter for 15 continuous minutes with the heaters operating.
In accordance with the Surveillance Frequency Control Program SR 3.7.3.2 Operate each Control Room Ventilation subsystem with flow through the recirculation filter for 15 minutes.
In accordance with the Surveillance Frequency Control Program (continued)  


Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4       Two control room AC subsystems shall be OPERABLE.
Control Room AC System 3.7.4 CLINTON 3.7-8 Amendment No. 95 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION           COMPLETION TIME A. One control room AC     A.1     Restore control room   30 days subsystem inoperable.            AC subsystem to OPERABLE status.
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
B. Two control room AC     B.1     Verify control room     Once per 4 hours subsystems inoperable.          area temperature 86 &#xba;F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC subsystem inoperable.
AND B.2     Restore one control     7 days room AC subsystem to OPERABLE status.
A.1 Restore control room AC subsystem to OPERABLE status.
C. Required Action and     -------------NOTE------------
30 days B. Two control room AC subsystems inoperable.
Associated Completion  LCO 3.0.4.a is not applicable Time of Condition A or  when entering MODE 3.
B.1 Verify control room area temperature 86 &#xba;F.
B not met in MODE 1,    -----------------------------
AND B.2 Restore one control room AC subsystem to OPERABLE status.
2, or 3.
Once per 4 hours 7 days C. Required Action and Associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.
C.1     Be in MODE 3.           12 hours (continued)
-------------NOTE------------
CLINTON                              3.7-8                    Amendment No. 95
LCO 3.0.4.a is not applicable when entering MODE 3.
C.1 Be in MODE 3.
12 hours (continued)  


Control Room AC System 3.7.4 ACTIONS (continued)
Control Room AC System 3.7.4 CLINTON 3.7-9 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION           COMPLETION TIME D. Required Action and   ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
associated Completion  LCO 3.0.3 is not applicable.
------------NOTE-------------
Time of Condition A    -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of irradiated D.1     Place OPERABLE         Immediately fuel assemblies in the          control room AC primary or secondary            subsystem in containment, or during          operation.
D.1 Place OPERABLE control room AC subsystem in operation.
CORE ALTERATIONS, or during OPDRVs.        OR D.2.1   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
OR D.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND D.2.2   Suspend CORE           Immediately ALTERATIONS.
AND D.2.2 Suspend CORE ALTERATIONS.
AND D.2.3   Initiate action to     Immediately suspend OPDRVs.
AND D.2.3 Initiate action to suspend OPDRVs.
(continued)
Immediately Immediately Immediately Immediately (continued)
CLINTON                            3.7-9                    Amendment No. 95


Control Room AC System 3.7.4 ACTIONS (continued)
Control Room AC System 3.7.4 CLINTON 3.7-10 Amendment No. 95 ACTIONS (continued)
CONDITION                   REQUIRED ACTION           COMPLETION TIME E. Required Action and     ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition B not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.
associated Completion    LCO 3.0.3 is not applicable.
------------NOTE-------------
Time of Condition B      -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of irradiated  E.1     Suspend movement of     Immediately fuel assemblies in the            irradiated fuel primary or secondary              assemblies in the containment, or during            primary and secondary CORE ALTERATIONS, or              containment.
E.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
during OPDRVs.
AND E.2 Suspend CORE ALTERATIONS.
AND E.2     Suspend CORE           Immediately ALTERATIONS.
AND E.3 Initiate action to suspend OPDRVs.
AND E.3     Initiate action to     Immediately suspend OPDRVs.
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the capability to remove the assumed heat load.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.7.4.1   Verify each control room AC subsystem has       In accordance the capability to remove the assumed heat       with the load.                                          Surveillance Frequency Control Program CLINTON                              3.7-10                    Amendment No. 95
In accordance with the Surveillance Frequency Control Program  


AC Sources Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources Shutdown LCO 3.8.2       The following AC electrical power sources shall be OPERABLE:
AC Sources Shutdown 3.8.2 CLINTON 3.8-16 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
: a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";
: a.
: b. One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and
One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";
: c. One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
: b.
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and
ACTIONS
: c.
One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
ACTIONS  
---------------------------------------NOTE----------------------------------
---------------------------------------NOTE----------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
(continued)
(continued)  
CLINTON                              3.8-16                  Amendment No. XXX


AC Sources Shutdown 3.8.2 ACTIONS (continued)
AC Sources Shutdown 3.8.2 CLINTON 3.8-17 Amendment No. 95 ACTIONS (continued)
CONDITION             REQUIRED ACTION           COMPLETION TIME A. LCO Item a not met. ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME A. LCO Item a not met.  
------------NOTE-------------
Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.
Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.
A.1     Declare affected       Immediately required feature(s) with no offsite power available from a required circuit inoperable.
A.1 Declare affected required feature(s) with no offsite power available from a required circuit inoperable.
OR A.2.1   Suspend CORE           Immediately ALTERATIONS.
OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
AND A.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND A.2.3   Initiate action to     Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
AND A.2.43   Initiate action to     Immediately restore required offsite power circuit to OPERABLE status.
AND A.2.43 Initiate action to restore required offsite power circuit to OPERABLE status.
(continued)
Immediately Immediately Immediately Immediately Immediately (continued)
CLINTON                            3.8-17                  Amendment No. 95


AC Sources Shutdown 3.8.2 ACTIONS (continued)
AC Sources Shutdown 3.8.2 CLINTON 3.8-18 Amendment No. 95 ACTIONS (continued)
CONDITION           REQUIRED ACTION         COMPLETION TIME B. LCO Item b not met. B.1   Suspend CORE           Immediately ALTERATIONS.
CONDITION REQUIRED ACTION COMPLETION TIME B. LCO Item b not met.
AND B.2   Suspend movement of   Immediately irradiated fuel assemblies in primary and secondary containment.
B.1 Suspend CORE ALTERATIONS.
AND B.3   Initiate action to     Immediately suspend OPDRVs.
AND B.2 Suspend movement of irradiated fuel assemblies in primary and secondary containment.
AND B.43   Initiate action to     Immediately restore required DG to OPERABLE status.
AND B.3 Initiate action to suspend OPDRVs.
C. LCO Item c not met. C.1   Declare High Pressure 72 hours Core Spray System inoperable.
AND B.43 Initiate action to restore required DG to OPERABLE status.
CLINTON                      3.8-18                  Amendment No. 95
Immediately Immediately Immediately Immediately C. LCO Item c not met.
C.1 Declare High Pressure Core Spray System inoperable.
72 hours


DC Sources Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5   DC Sources Shutdown LCO 3.8.5       The following shall be OPERABLE:
DC Sources Shutdown 3.8.5 CLINTON 3.8-27 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 The following shall be OPERABLE:
: a. One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -
: a.
One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -
Shutdown";
Shutdown";
: b. One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and
: b.
: c. The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
: c.
ACTIONS
The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. One battery charger       A.1     Restore battery         2 hours on one division                    terminal voltage to inoperable.                      greater than or equal to the minimum established float voltage.
CONDITION REQUIRED ACTION COMPLETION TIME A.
AND A.2     Verify battery float   Once per 12 current < 2 amps.       hours AND A.3     Restore battery         7 days charger to OPERABLE status.
One battery charger on one division inoperable.
(continued)
A.1 Restore battery terminal voltage to greater than or equal to the minimum established float voltage.
CLINTON                              3.8-27                    Amendment No. XXX
AND A.2 Verify battery float current < 2 amps.
AND A.3 Restore battery charger to OPERABLE status.
2 hours Once per 12 hours 7 days (continued)  


DC Sources Shutdown 3.8.5 ACTIONS (continued)
DC Sources Shutdown 3.8.5 CLINTON 3.8-28 Amendment No. 142 ACTIONS (continued)
CONDITION                 REQUIRED ACTION           COMPLETION TIME B. One or more required   B.1      Declare affected        Immediately DC electrical power             required feature(s) subsystems inoperable           inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required DC electrical power subsystems inoperable for reasons other than Condition A.
for reasons other than Condition A.           OR OR B.2.1    Suspend CORE            Immediately Required Action and             ALTERATIONS.
OR Required Action and associated Completion Time of Condition A not met.
associated Completion Time of Condition A       AND not met.
B.1 Declare affected required feature(s) inoperable.
B.2.2   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
OR B.2.1 Suspend CORE ALTERATIONS.
AND B.2.3   Initiate action to     Immediately suspend operations with a potential for draining the reactor.
AND Immediately Immediately B.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND B.2.43   Initiate action to     Immediately restore required DC electrical power subsystems to OPERABLE status.
AND Immediately B.2.3 Initiate action to suspend operations with a potential for draining the reactor.
CLINTON                            3.8-28                    Amendment No. 142
Immediately AND B.2.43 Initiate action to restore required DC electrical power subsystems to OPERABLE status.
Immediately


Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters Shutdown LCO 3.8.8       The following Divisional inverters shall be OPERABLE:
Inverters-Shutdown 3.8.8 CLINTON 3.8-36 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters Shutdown LCO 3.8.8 The following Divisional inverters shall be OPERABLE:
: a. One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and
: a.
: b. The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
: b.
CLINTON                              3.8-36                  Amendment No. XXX
The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.  


Inverters Shutdown 3.8.8 ACTIONS
Inverters Shutdown 3.8.8 CLINTON 3.8-37 Amendment No. 95 ACTIONS  
------------------------------------------NOTE-------------------------------
------------------------------------------NOTE-------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
CONDITION                 REQUIRED ACTION           COMPLETION TIME A. One or more required   A.1     Declare affected       Immediately divisional inverters            required feature(s) inoperable.                      inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required divisional inverters inoperable.
OR A.2.1   Suspend CORE           Immediately ALTERATIONS.
A.1 Declare affected required feature(s) inoperable.
AND A.2.2   Suspend handling of     Immediately irradiated fuel assemblies in the primary and secondary containment.
OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.3   Initiate action to     Immediately suspend operations with a potential for draining the reactor vessel.
AND Immediately Immediately A.2.2 Suspend handling of irradiated fuel assemblies in the primary and secondary containment.
AND A.2.43   Initiate action to     Immediately restore required divisional inverters to OPERABLE status.
AND Immediately A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.
CLINTON                            3.8-37                      Amendment No. 95
AND Immediately A.2.43 Initiate action to restore required divisional inverters to OPERABLE status.
Immediately


Distribution Systems Shutdown 3.8.10 ACTIONS (continued)
Distribution Systems Shutdown 3.8.10 CLINTON 3.8-43 Amendment No. 192 ACTIONS (continued)
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. (continued)             A.2.3   Initiate action to     Immediately suspend operations with a potential for draining the reactor vessel.
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
AND A.2.43   Initiate actions to     Immediately restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.
A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.
AND A.2.54   Declare associated     Immediately required shutdown cooling subsystem(s) inoperable and not in operation.
AND A.2.43 Initiate actions to restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.8.10.1   Verify correct breaker alignments and           In accordance voltage to required AC, DC, and                 with the uninterruptible AC bus electrical power         Surveillance distribution subsystems.                       Frequency Control Program CLINTON                              3.8-43                  Amendment No. 192
AND A.2.54 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and uninterruptible AC bus electrical power distribution subsystems.
In accordance with the Surveillance Frequency Control Program  


Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 3 REVISED TECHNICAL SPECIFICATIONS PAGES TOC Page ii                       3.3-48                          3.6-7 TOC Page iii                       3.3-49                          3.6-9 TOC Page iv                       3.3-50                          3.6-14 1.0-1                         3.3-51                          3.6-43 1.0-2                          3.3-52                          3.6-44 1.0-3                          3.3-53                          3.6-47 1.0-4                          3.3-54                          3.6-49 1.0-5                          3.3-55                          3.6-51 3.3-32                          3.3-56                          3.6-52 3.3-33                          3.3-57                          3.6-53 3.3-35                          3.3-58                          3.7-4 3.3-39                          3.3-59                          3.7-5 3.3-40                          3.3-60                          3.7-6 3.3-41                          3.3-64                          3.7-8 3.3-42                          3.3-77                         3.7-9 3.3-43                          3.5-1                          3.7-10 3.3-43a                          3.5-6                          3.8-16 3.3-43b                          3.5-7                         3.8-17 3.3-43c                          3.5-8                          3.8-18 3.3-43d                          3.5-9                          3.8-27 3.3-44                          3.5-10                          3.8-28 3.3-45                          3.5-11                          3.8-36 3.3-46                          3.5-12                          3.8-37 3.3-47                          3.6-3                          3.8-43
Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 3 REVISED TECHNICAL SPECIFICATIONS PAGES TOC Page ii TOC Page iii TOC Page iv 1.0-1 1.0-2 1.0-3 1.0-4 1.0-5 3.3-32 3.3-33 3.3-35 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-45 3.3-46 3.3-47 3.3-48 3.3-49 3.3-50 3.3-51 3.3-52 3.3-53 3.3-54 3.3-55 3.3-56 3.3-57 3.3-58 3.3-59 3.3-60 3.3-64 3.3-77 3.5-1 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 3.6-3 3.6-7 3.6-9 3.6-14 3.6-43 3.6-44 3.6-47 3.6-49 3.6-51 3.6-52 3.6-53 3.7-4 3.7-5 3.7-6 3.7-8 3.7-9 3.7-10 3.8-16 3.8-17 3.8-18 3.8-27 3.8-28 3.8-36 3.8-37 3.8-43  


TABLE OF CONTENTS 3.2     POWER DISTRIBUTION LIMITS (continued) 3.2.2   MINIMUM CRITICAL POWER RATIO (MCPR)...........................3.2-2 3.2.3   LINEAR HEAT GENERATION RATE (LHGR) ...........................3.2-3 B 3.2   POWER DISTRIBUTION LIMITS.....................................B   3.2-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)..................................................B   3.2-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)...........................B   3.2-5 B 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)............................B   3.2-9 3.3     INSTRUMENTATION...............................................3.3-1 3.3.1.1     Reactor Protection System (RPS) Instrumentation...........3.3-1 3.3.1.2     Source Range Monitor (SRM) Instrumentation................3.3-10 3.3.1.3     Oscillation Power Range Monitor (OPRM) Instrumentation....3.3-14a 3.3.2.1     Control Rod Block Instrumentation.........................3.3-15 3.3.3.1     Post Accident Monitoring (PAM) Instrumentation............3.3-19 3.3.3.2     Remote Shutdown System....................................3.3-23 3.3.4.1     End of Cycle Recirculation Pump Trip (EOC-RPT)
TABLE OF CONTENTS CLINTON Revision No. 14-2 ii 3.2 POWER DISTRIBUTION LIMITS (continued) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)...........................3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)...........................3.2-3 B 3.2 POWER DISTRIBUTION LIMITS.....................................B 3.2-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)..................................................B 3.2-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)...........................B 3.2-5 B 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)............................B 3.2-9 3.3 INSTRUMENTATION...............................................3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation...........3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation................3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation....3.3-14a 3.3.2.1 Control Rod Block Instrumentation.........................3.3-15 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation............3.3-19 3.3.3.2 Remote Shutdown System....................................3.3-23 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation.......................................3.3-25 3.3.4.2     Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation..................3.3-28 3.3.5.1     Emergency Core Cooling System (ECCS) Instrumentation......3.3-31 3.3.5.2     Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation ................................... 3.3-43a 3.3.5.3     Reactor Core Isolation Cooling (RCIC) System Instrumentation ................................... 3.3-44 3.3.6.1     Primary Containment and Drywell Isolation Instrumentation.3.3-48 3.3.6.2     Secondary Containment Isolation Instrumentation...........3.3-61 3.3.6.3     Residual Heat Removal (RHR) Containment Spray System Instrumentation.......................................3.3-65 3.3.6.4     Suppression Pool Makeup (SPMU) System Instrumentation.....3.3-69 3.3.6.5     Relief and Low-Low Set (LLS) Instrumentation..............3.3-74 3.3.7.1     Control Room Ventilation System Instrumentation...........3.3-75 3.3.8.1     Loss of Power (LOP) Instrumentation.......................3.3-78 3.3.8.2     Reactor Protection System (RPS) Electric Power Monitoring.3.3-81 B 3.3   INSTRUMENTATION............................................. B 3.3-1 B 3.3.1.1   Reactor Protection System (RPS) Instrumentation......... B 3.3-1 B 3.3.1.2   Source Range Monitor (SRM) Instrumentation.............. B 3.3-31 B 3.3.1.3   Oscillation Power Range Monitor (OPRM) Instrumentation.. B 3.3-39a B 3.3.2.1   Control Rod Block Instrumentation....................... B 3.3-40 B 3.3.3.1   Post Accident Monitoring (PAM) Instrumentation.......... B 3.3-49 (continued)
Instrumentation.......................................3.3-25 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation..................3.3-28 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......3.3-31 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation................................... 3.3-43a 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation................................... 3.3-44 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.3.3-48 3.3.6.2 Secondary Containment Isolation Instrumentation...........3.3-61 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation.......................................3.3-65 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....3.3-69 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............3.3-74 3.3.7.1 Control Room Ventilation System Instrumentation...........3.3-75 3.3.8.1 Loss of Power (LOP) Instrumentation.......................3.3-78 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.3.3-81 B 3.3 INSTRUMENTATION............................................. B 3.3-1 B 3.3.1.1 Reactor Protection System (RPS) Instrumentation......... B 3.3-1 B 3.3.1.2 Source Range Monitor (SRM) Instrumentation.............. B 3.3-31 B 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation.. B 3.3-39a B 3.3.2.1 Control Rod Block Instrumentation....................... B 3.3-40 B 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation.......... B 3.3-49 (continued)  
CLINTON                                                      Revision No. 14-2 ii


TABLE OF CONTENTS B 3.3   INSTRUMENTATION (continued)
TABLE OF CONTENTS CLINTON Revision No. 2-13 iii B 3.3 INSTRUMENTATION (continued)
B 3.3.3.2   Remote Shutdown System....................................B   3.3-60 B 3.3.4.1   End of Cycle Recirculation Pump Trip (EOC-RPT)
B 3.3.3.2 Remote Shutdown System....................................B 3.3-60 B 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation...........................................B   3.3-65 B 3.3.4.2   Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B   3.3-76 B 3.3.5.1   Emergency Core Cooling System (ECCS) Instrumentation......B   3.3-85 B 3.3.5.2   Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation ...................................... B 3.3-122a B 3.3.5.3   Reactor Core Isolation Cooling (RCIC) System Instrumentation ...................................... B 3.3-123 B 3.3.6.1   Primary Containment and Drywell Isolation Instrumentation .........................B 3.3-135 B 3.3.6.2   Secondary Containment Isolation Instrumentation...........B   3.3-174 B 3.3.6.3   Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B   3.3-186 B 3.3.6.4   Suppression Pool Makeup (SPMU) System Instrumentation.....B   3.3-197 B 3.3.6.5   Relief and Low-Low Set (LLS) Instrumentation..............B   3.3-208 B 3.3.7.1   Control Room Ventilation (CRV) System Instrumentation.....B   3.3-215 B 3.3.8.1   Loss of Power (LOP) Instrumentation.......................B   3.3-222 B 3.3.8.2   Reactor Protection System (RPS) Electric Power Monitoring .....................................B 3.3-230 3.4     REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1       Recirculation Loops Operating.............................3.4-1 3.4.2       Flow Control Valves (FCVs)................................3.4-6 3.4.3       Jet Pumps.................................................3.4-8 3.4.4       Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5       RCS Operational LEAKAGE...................................3.4-12 3.4.6       RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7       RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8       RCS Specific Activity.....................................3.4-20 3.4.9       Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ......................................3.4-22 3.4.10       Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .....................................3.4-25 3.4.11       RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12       Reactor Steam Dome Pressure...............................3.4-33 B 3.4   REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1     Recirculation Loops Operating.............................B 3.4-1 B 3.4.2     Flow Control Valves (FCVs)................................B 3.4-9 (continued)
Instrumentation...........................................B 3.3-65 B 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B 3.3-76 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......B 3.3-85 B 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation...................................... B 3.3-122a B 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123 B 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.........................B 3.3-135 B 3.3.6.2 Secondary Containment Isolation Instrumentation...........B 3.3-174 B 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B 3.3-186 B 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....B 3.3-197 B 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............B 3.3-208 B 3.3.7.1 Control Room Ventilation (CRV) System Instrumentation.....B 3.3-215 B 3.3.8.1 Loss of Power (LOP) Instrumentation.......................B 3.3-222 B 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.....................................B 3.3-230 3.4 REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1 Recirculation Loops Operating.............................3.4-1 3.4.2 Flow Control Valves (FCVs)................................3.4-6 3.4.3 Jet Pumps.................................................3.4-8 3.4.4 Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5 RCS Operational LEAKAGE...................................3.4-12 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7 RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8 RCS Specific Activity.....................................3.4-20 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown......................................3.4-22 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.....................................3.4-25 3.4.11 RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12 Reactor Steam Dome Pressure...............................3.4-33 B 3.4 REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1 Recirculation Loops Operating.............................B 3.4-1 B 3.4.2 Flow Control Valves (FCVs)................................B 3.4-9 (continued)  
CLINTON                                                        Revision No. 2-13 iii


TABLE OF CONTENTS B 3.4   REACTOR COOLANT SYSTEM (RCS) (continued)
TABLE OF CONTENTS CLINTON Revision No. 14-2 iv B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)
B 3.4.3     Jet Pumps.................................................B   3.4-13 B 3.4.4     Safety/Relief Valves (S/RVs)..............................B   3.4-17 B 3.4.5     RCS Operational LEAKAGE...................................B   3.4-23 B 3.4.6     RCS Pressure Isolation Valve (PIV) Leakage................B   3.4-28 B 3.4.7     RCS Leakage Detection Instrumentation.....................B   3.4-33 B 3.4.8     RCS Specific Activity.....................................B   3.4-39 B 3.4.9     Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................B 3.4-43 B 3.4.10     Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .................................B 3.4-48 B 3.4.11     RCS Pressure and Temperature (P/T) Limits.................B   3.4-53 B 3.4.12     Reactor Steam Dome Pressure...............................B   3.4-63 3.5     EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
B 3.4.3 Jet Pumps.................................................B 3.4-13 B 3.4.4 Safety/Relief Valves (S/RVs)..............................B 3.4-17 B 3.4.5 RCS Operational LEAKAGE...................................B 3.4-23 B 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................B 3.4-28 B 3.4.7 RCS Leakage Detection Instrumentation.....................B 3.4-33 B 3.4.8 RCS Specific Activity.....................................B 3.4-39 B 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown..................................B 3.4-43 B 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................B 3.4-48 B 3.4.11 RCS Pressure and Temperature (P/T) Limits.................B 3.4-53 B 3.4.12 Reactor Steam Dome Pressure...............................B 3.4-63 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................3.5-1 3.5.1       ECCS - Operating ...........................................3.5-1 3.5.2       RPV Water Inventory Control...............................3.5-6 3.5.3       RCIC System...............................................3.5-11 B 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................3.5-1 3.5.1 ECCS - Operating...........................................3.5-1 3.5.2 RPV Water Inventory Control...............................3.5-6 3.5.3 RCIC System...............................................3.5-11 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................B 3.5-1 B 3.5.1     ECCS - Operating ...........................................B 3.5-1 B 3.5.2     RPV Water Inventory Control...............................B 3.5-17 B 3.5.3     RCIC System...............................................B 3.5-27 3.6     CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1     Primary Containment.......................................3.6-1 3.6.1.2     Primary Containment Air Locks.............................3.6-3 3.6.1.3     Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4     Primary Containment Pressure..............................3.6-20 3.6.1.5     Primary Containment Air Temperature.......................3.6-21 3.6.1.6     Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7     Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8     Deleted...................................................3.6-26 3.6.1.9     Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1     Suppression Pool Average Temperature......................3.6-28 3.6.2.2     Suppression Pool Water Level..............................3.6-31 3.6.2.3     Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4     Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1     Deleted .................................................3.6-36 3.6.3.2     Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................B 3.5-1 B 3.5.1 ECCS - Operating...........................................B 3.5-1 B 3.5.2 RPV Water Inventory Control...............................B 3.5-17 B 3.5.3 RCIC System...............................................B 3.5-27 3.6 CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1 Primary Containment.......................................3.6-1 3.6.1.2 Primary Containment Air Locks.............................3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4 Primary Containment Pressure..............................3.6-20 3.6.1.5 Primary Containment Air Temperature.......................3.6-21 3.6.1.6 Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7 Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8 Deleted...................................................3.6-26 3.6.1.9 Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1 Suppression Pool Average Temperature......................3.6-28 3.6.2.2 Suppression Pool Water Level..............................3.6-31 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4 Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1 Deleted.................................................3.6-36 3.6.3.2 Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)  
CLINTON                                                          Revision No. 14-2 iv


Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions
Definitions 1.1 CLINTON 1.0-1 Amendment No. 105 1.0 USE AND APPLICATION 1.1 Definitions  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term                       Definition ACTIONS                     ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR       The APLHGR shall be applicable to a specific HEAT GENERATION RATE       planar height and is equal to the sum of the (APLHGR)                   LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR)
CHANNEL CALIBRATION         A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.
LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL CHECK               A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST     A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
(continued)
(continued)  
CLINTON                              1.0-1                  Amendment No. 105


Definitions 1.1 1.1 Definitions (continued)
Definitions 1.1 CLINTON 1.0-2 Amendment No. 105 1.1 Definitions (continued)
CORE ALTERATION             CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
and
and
: b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
: b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS       The COLR is the unit specific document that REPORT (COLR)               provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131       DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.
DRAIN TIME                 The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
: a. The water inventory above the TAF is divided by the limiting drain rate;
: a.
: b. The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,
The water inventory above the TAF is divided by the limiting drain rate;
: b.
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,
seismic event, loss of normal power, single human error), for all (continued)
seismic event, loss of normal power, single human error), for all (continued)
CLINTON                              1.0-2                    Amendment No. 105


Definitions 1.1 Definitions DRAIN TIME                 penetration flow paths below the TAF except:
Definitions 1.1 CLINTON 1.0-3 Amendment No. 105 Definitions DRAIN TIME penetration flow paths below the TAF except:
(continued)
(continued)
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
Line 977: Line 1,235:
: e. Realistic cross-sectional areas and drain rates are used.
: e. Realistic cross-sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in lieu of a calculated value.
A bounding DRAIN TIME may be used in lieu of a calculated value.
EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME                   initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
(continued)
CLINTON                        1.0-3                    Amendment No. 105


Definitions 1.1 1.1 Definitions (continued)
Definitions 1.1 CLINTON 1.0-4 Amendment No. 105 1.1 Definitions (continued)
END OF CYCLE               The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP     time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE   associated turbine stop valve or turbine TIME                       control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE associated turbine stop valve or turbine TIME control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
INSERVICE TESTING           The INSERVICE TESTING PROGRAM is the licensee PROGRAM                     program that fulfills the requirements of 10 CFR 50.55a(f).
INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).
ISOLATION SYSTEM           The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME               time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
LEAKAGE                     LEAKAGE shall be:
LEAKAGE LEAKAGE shall be:
: a. Identified LEAKAGE
: a. Identified LEAKAGE
: 1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
: 1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
Line 992: Line 1,249:
: c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
: c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
(continued)
(continued)  
CLINTON                              1.0-4                  Amendment No. 105


Definitions 1.1 1.1   Definitions (continued)
Definitions 1.1 CLINTON 1.0-5 Amendment No. 95 128 1.1 Definitions (continued)
LINEAR HEAT GENERATION       The LHGR shall be the heat generation rate per RATE (LHGR)                 unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL     A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST                         of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
MINIMUM CRITICAL POWER       The MCPR shall be the smallest critical power RATIO (MCPR)                 ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MODE                         A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLE OPERABILITY       A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
OPERABLE OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RATED THERMAL POWER         RTP shall be a total reactor core heat transfer (RTP)                       rate to the reactor coolant of 3473 MWt.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3473 MWt.
REACTOR PROTECTION           The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE       from when the monitored parameter exceeds its RPS TIME                         trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
(continued)  
CLINTON                              1.0-5                  Amendment No. 95 128


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-32 Amendment No. 95 ACTIONS (continued)
CONDITION               REQUIRED ACTION         COMPLETION TIME B. As required by     B.1   --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action A.1      Only applicable for and referenced in        Functions 1.a, 1.b, Table 3.3.5.1-1.          2.a, and 2.b.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Declare supported         1 hour from feature(s) inoperable     discovery of when its redundant       loss of feature ECCS initiation  initiation capability is             capability for inoperable.              feature(s) in both divisions AND B.2   --------NOTE---------
B.1  
--------NOTE---------
Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions B.2  
--------NOTE---------
Only applicable for Functions 3.a and 3.b.
Only applicable for Functions 3.a and 3.b.
Declare High Pressure     1 hour from Core Spray (HPCS)         discovery of System inoperable.       loss of HPCS initiation capability AND B.3   Place channel in trip. 24 hours (continued)
Declare High Pressure Core Spray (HPCS)
CLINTON                        3.3-32                      Amendment No. 95
System inoperable.
AND B.3 Place channel in trip.
1 hour from discovery of loss of HPCS initiation capability 24 hours (continued)  


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-33 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION       COMPLETION TIME C. As required by     C.1   ---------NOTE--------
CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Action A.1      Only applicable for and referenced in        Functions 1.c, 1.d, Table 3.3.5.1-1.          2.c, and 2.d.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Declare supported       1 hour from feature(s) inoperable   discovery of when its redundant       loss of feature ECCS             initiation initiation capability   capability for is inoperable.           feature(s) in both divisions AND C.2   Restore channel to       24 hours OPERABLE status.
C.1  
(continued)
---------NOTE--------
CLINTON                        3.3-33                      Amendment No. 95
Only applicable for Functions 1.c, 1.d, 2.c, and 2.d.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions C.2 Restore channel to OPERABLE status.
24 hours (continued)  


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-35 Amendment No. 95 ACTIONS (continued)
CONDITION               REQUIRED ACTION       COMPLETION TIME E. As required by     E.1   --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME E.
Required Action A.1      Only applicable for and referenced in            Functions 1.e, Table 3.3.5.1-1.              1.f, and 2.e.
As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Declare supported       1 hour from feature(s) inoperable   discovery of when its redundant       loss of feature ECCS             initiation initiation capability   capability for is inoperable.           feature(s) in both divisions AND E.2   Restore channel to       7 days OPERABLE status.
E.1  
(continued)
--------NOTE---------
CLINTON                        3.3-35                      Amendment No. 95
Only applicable for Functions 1.e, 1.f, and 2.e.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND E.2 Restore channel to OPERABLE status.
1 hour from discovery of loss of initiation capability for feature(s) in both divisions 7 days (continued)  


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-39 Amendment No. 169 Table 3.3.5.1-1 (page 1 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER       REQUIRED       FROM SPECIFIED      CHANNELS     REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS         PER      ACTION A.1   REQUIREMENTS       VALUE FUNCTION
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
Subsystems
: a. Reactor Vessel Water         1,2,3           2(a)         B     SR   3.3.5.1.1     -148.1 Level-Low Low Low,                                              SR   3.3.5.1.2   inches Level 1                                                          SR   3.3.5.1.3(c)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 2(a)
SR   3.3.5.1.5 SR   3.3.5.1.6(c)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: b. Drywell Pressure-High       1,2,3           2(a)         B     SR   3.3.5.1.1     1.88 psig SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(c)  
: c. LPCI Pump A                 1,2,3           1           C     SR   3.3.5.1.2     4.5 seconds Start-Time Delay                                                SR   3.3.5.1.4   and Logic Card                                                      SR   3.3.5.1.5     5.5 seconds
-148.1 inches
: d. Reactor Vessel               1,2,3           4           C     SR   3.3.5.1.1     454 psig Pressure-Low                                                    SR   3.3.5.1.2   and (Injection Permissive)                                          SR   3.3.5.1.3(c) 494 psig SR   3.3.5.1.4(c)
: b. Drywell Pressure-High 1,2,3 2(a)
SR   3.3.5.1.5
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
: e. LPCS Pump Discharge           1,2,3           1           E     SR   3.3.5.1.1     750 gpm Flow-Low (Bypass)                                                SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
: c. LPCI Pump A Start-Time Delay Logic Card 1,2,3 1
: f. LPCI Pump A Discharge       1,2,3           1           E     SR   3.3.5.1.1     900 gpm Flow-Low (Bypass)                                                SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds
: g. Manual Initiation             1,2,3           1           C     SR   3.3.5.1.5   NA (continued)
: d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4
C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 454 psig and 494 psig
: e. LPCS Pump Discharge Flow-Low (Bypass) 1,2,3 1
E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 750 gpm
: f. LPCI Pump A Discharge Flow-Low (Bypass) 1,2,3 1
E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm
: g. Manual Initiation 1,2,3 1
C SR 3.3.5.1.5 NA (continued)
(a) Also required to initiate the associated diesel generator.
(a) Also required to initiate the associated diesel generator.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                      3.3-39                            Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-40 Amendment No. 169 Table 3.3.5.1-1 (page 2 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES OR                   REFERENCED OTHER       REQUIRED       FROM SPECIFIED    CHANNELS PER   REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS       FUNCTION    ACTION A.1   REQUIREMENTS     VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. LPCI B and LPCI C Subsystems
: 2. LPCI B and LPCI C Subsystems
: a. Reactor Vessel             1,2,3           2(a)         B     SR   3.3.5.1.1     -148.1 Water Level-Low Low                                            SR   3.3.5.1.2   inches Low, Level 1                                                  SR   3.3.5.1.3(c)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 2(a)
SR   3.3.5.1.5 SR   3.3.5.1.6(c)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: b. Drywell Pressure-         1,2,3           2(a)         B     SR   3.3.5.1.1     1.88 psig High                                                          SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(c)  
: c. LPCI Pump B               1,2,3           1           C     SR   3.3.5.1.2     4.5 seconds Start-Time Delay                                              SR   3.3.5.1.4   and Logic Card                                                    SR   3.3.5.1.5     5.5 seconds
-148.1 inches
: d. Reactor Vessel             1,2,3           4           C     SR   3.3.5.1.1     454 psig Pressure-Low                                                  SR   3.3.5.1.2   and (Injection                                                    SR   3.3.5.1.3(c) 494 psig Permissive)                                                    SR   3.3.5.1.4(c)
: b. Drywell Pressure-High 1,2,3 2(a)
SR   3.3.5.1.5
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
: e. LPCI Pump B and           1,2,3       1 per pump       E     SR   3.3.5.1.1     900 gpm LPCI Pump C                                                    SR   3.3.5.1.2 Discharge Flow-Low                                            SR   3.3.5.1.3 (Bypass)                                                      SR   3.3.5.1.4 SR   3.3.5.1.5
: c. LPCI Pump B Start-Time Delay Logic Card 1,2,3 1
: f. Manual Initiation         1,2,3             1           C     SR   3.3.5.1.5   NA (continued)
C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds
: d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4
C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 454 psig and 494 psig
: e. LPCI Pump B and LPCI Pump C Discharge Flow-Low (Bypass) 1,2,3 1 per pump E
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm
: f. Manual Initiation 1,2,3 1
C SR 3.3.5.1.5 NA (continued)
(a) Also required to initiate the associated diesel generator.
(a) Also required to initiate the associated diesel generator.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                    3.3-40                            Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-41 Amendment No. 169 Table 3.3.5.1-1 (page 3 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER     REQUIRED       FROM SPECIFIED  CHANNELS PER   REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS     FUNCTION    ACTION A.1   REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. High Pressure Core Spray (HPCS) System
: 3. High Pressure Core Spray (HPCS) System
: a. Reactor Vessel Water       1,2,3         4(a)         B     SR   3.3.5.1.1     -48.1 inches Level-Low Low,                                                SR   3.3.5.1.2 Level 2                                                      SR   3.3.5.1.3(c)
: a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4(a)
SR   3.3.5.1.5 SR   3.3.5.1.6(c)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: b. Drywell                     1,2,3         4(a)         B     SR   3.3.5.1.1     1.88 psig Pressure - High                                              SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(c)  
: c. Reactor Vessel Water       1,2,3         2           C     SR   3.3.5.1.1     54.6 inches Level-High,                                                  SR   3.3.5.1.2 Level 8                                                      SR   3.3.5.1.3(c)
-48.1 inches
SR   3.3.5.1.5 SR   3.3.5.1.6(c)
: b. Drywell Pressure - High 1,2,3 4(a)
: d. RCIC Storage Tank           1,2,3         2           D     SR   3.3.5.1.1     3.0 inches Level-Low                                                    SR   3.3.5.1.2 SR   3.3.5.1.3(c)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR   3.3.5.1.4(c)
: c. Reactor Vessel Water Level-High, Level 8 1,2,3 2
SR   3.3.5.1.5
C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: e. Suppression Pool           1,2,3         2           D     SR   3.3.5.1.1     11 inches Water Level-High                                              SR   3.3.5.1.2 SR   3.3.5.1.3(c)
SR 3.3.5.1.5 SR 3.3.5.1.6(c) 54.6 inches
SR   3.3.5.1.4(c)
: d. RCIC Storage Tank Level-Low 1,2,3 2
SR   3.3.5.1.5
D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: f. HPCS Pump                   1,2,3         1           E     SR   3.3.5.1.1     120 psig Discharge                                                    SR   3.3.5.1.2 Pressure-High                                                SR   3.3.5.1.3 (Bypass)                                                      SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.4(c)
: g. HPCS System Flow           1,2,3         1           E     SR   3.3.5.1.1     500 gpm Rate-Low (Bypass)                                            SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 3.0 inches
: h. Manual Initiation         1,2,3           1           C     SR   3.3.5.1.5   NA (continued)
: e. Suppression Pool Water Level-High 1,2,3 2
D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 11 inches
: f. HPCS Pump Discharge Pressure-High (Bypass) 1,2,3 1
E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 120 psig
: g. HPCS System Flow Rate-Low (Bypass) 1,2,3 1
E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 500 gpm
: h. Manual Initiation 1,2,3 1
C SR 3.3.5.1.5 NA (continued)
(a) Also required to initiate the associated diesel generator.
(a) Also required to initiate the associated diesel generator.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                    3.3-41                            Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-42 Amendment No. 169 Table 3.3.5.1-1 (page 4 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES OR                   REFERENCED OTHER       REQUIRED       FROM SPECIFIED    CHANNELS PER   REQUIRED      SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS       FUNCTION    ACTION A.1     REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
: 4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
: a. Reactor Vessel Water   1,2(b),3(b)         2           F     SR   3.3.5.1.1     -148.1 inches Level-Low Low Low,                                              SR   3.3.5.1.2 Level 1                                                        SR   3.3.5.1.3(c)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(b),3(b) 2 F
SR   3.3.5.1.5 SR   3.3.5.1.6(c)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: b. Drywell                 1,2(b),3(b)         2           F     SR   3.3.5.1.1     1.88 psig Pressure-High                                                  SR   3.3.5.1.2 SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(c)  
: c. ADS Initiation Timer   1,2(b),3(b)         1           G     SR   3.3.5.1.2     117 seconds SR   3.3.5.1.4 SR   3.3.5.1.5
-148.1 inches
: d. Reactor Vessel Water   1,2(b),3(b)         1           F     SR   3.3.5.1.1     8.3 inches Level-Low, Level 3                                              SR   3.3.5.1.2 (Confirmatory)                                                  SR   3.3.5.1.3 SR   3.3.5.1.4 SR   3.3.5.1.5
: b. Drywell Pressure-High 1,2(b),3(b) 2 F
: e. LPCS Pump Discharge     1,2(b),3(b)         2           G     SR   3.3.5.1.1     125 psig and Pressure-High                                                  SR   3.3.5.1.2   < 176.3 psig SR   3.3.5.1.3(c)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR   3.3.5.1.4(c)
: c. ADS Initiation Timer 1,2(b),3(b) 1 G
SR   3.3.5.1.5
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds
: f. LPCI Pump A             1,2(b),3(b)         2           G     SR   3.3.5.1.1     115 psig and Discharge Pressure-                                            SR   3.3.5.1.2   < 135 psig High                                                            SR   3.3.5.1.3(c)
: d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F
SR   3.3.5.1.4(c)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches
SR   3.3.5.1.5
: e. LPCS Pump Discharge Pressure-High 1,2(b),3(b) 2 G
: g. ADS Drywell Pressure   1,2(b),3(b)         2           G     SR   3.3.5.1.2     6.5 minutes Bypass Timer                                                    SR   3.3.5.1.4 SR   3.3.5.1.5
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: h. Manual Initiation       1,2(b),3(b)         2           G     SR   3.3.5.1.5   NA (continued)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 125 psig and
< 176.3 psig
: f. LPCI Pump A Discharge Pressure-High 1,2(b),3(b) 2 G
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 115 psig and
< 135 psig
: g. ADS Drywell Pressure Bypass Timer 1,2(b),3(b) 2 G
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes
: h. Manual Initiation 1,2(b),3(b) 2 G
SR 3.3.5.1.5 NA (continued)
(b) With reactor steam dome pressure > 150 psig.
(b) With reactor steam dome pressure > 150 psig.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.  
CLINTON                                      3.3-42                              Amendment No. 169


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)
ECCS Instrumentation 3.3.5.1 CLINTON 3.3-43 Amendment No. 169 Table 3.3.5.1-1 (page 5 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER       REQUIRED     FROM SPECIFIED    CHANNELS PER REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS     FUNCTION  ACTION A.1   REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. ADS Trip System 2 (Logic B and F)
: 5. ADS Trip System 2 (Logic B and F)
: a. Reactor Vessel Water       1,2(b),3(b)       2           F     SR 3.3.5.1.1     -148.1 Level-Low Low Low,                                              SR 3.3.5.1.2     inches Level 1                                                        SR 3.3.5.1.3(c)
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(b),3(b) 2 F
SR 3.3.5.1.5 SR 3.3.5.1.6(c)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
: b. Drywell Pressure-High     1,2(b),3(b)       2           F     SR 3.3.5.1.1     1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5
SR 3.3.5.1.5 SR 3.3.5.1.6(c)  
: c. ADS Initiation Timer       1,2(b),3(b)       1           G     SR 3.3.5.1.2     117 seconds SR 3.3.5.1.4 SR 3.3.5.1.5
-148.1 inches
: d. Reactor Vessel Water       1,2(b),3(b)       1           F     SR 3.3.5.1.1     8.3 inches Level-Low, Level 3                                              SR 3.3.5.1.2 (Confirmatory)                                                  SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5
: b. Drywell Pressure-High 1,2(b),3(b) 2 F
: e. LPCI Pumps B & C           1,2(b),3(b)   2 per pump       G     SR 3.3.5.1.1     115 psig Discharge                                                      SR 3.3.5.1.2     and  135 Pressure-High                                                  SR 3.3.5.1.3(c) psig SR 3.3.5.1.4(c)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig
SR 3.3.5.1.5
: c. ADS Initiation Timer 1,2(b),3(b) 1 G
: f. ADS Drywell Pressure       1,2(b),3(b)       2           G     SR 3.3.5.1.2     6.5 minutes Bypass Timer                                                    SR 3.3.5.1.4 SR 3.3.5.1.5
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds
: g. Manual Initiation         1,2(b),3(b)       2           G     SR 3.3.5.1.5   NA (b) With reactor steam dome pressure > 150 psig.
: d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches
: e. LPCI Pumps B & C Discharge Pressure-High 1,2(b),3(b) 2 per pump G
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)
SR 3.3.5.1.4(c)
SR 3.3.5.1.5 115 psig and 135 psig
: f. ADS Drywell Pressure Bypass Timer 1,2(b),3(b) 2 G
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes
: g. Manual Initiation 1,2(b),3(b) 2 G
SR 3.3.5.1.5 NA (b) With reactor steam dome pressure > 150 psig.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
: 3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.
CLINTON                                      3.3-43                          Amendment No. 169


RPV Water Inventory Control Instrumentation 3.3.5.2 3.3   INSTRUMENTATION 3.3.5.2       Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2       The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43a Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
APPLICABILITY:     According to Table 3.3.5.2-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.5.2-1.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. One or more channels   A.1   Enter the Condition       Immediately inoperable.                    referenced in Table 3.3.5.2-1 for the channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
B. As required by         B.1    Declare associated        Immediately Required Action A.1           penetration flow and referenced in             path(s) incapable of Table 3.3.5.2-1.               automatic isolation.
A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel.
AND B.2   Calculate DRAIN TIME. Immediately C. As required by         C.1    Place channel in trip. 1 hour Required Action A.1 and referenced in Table 3.3.5.2-1.
Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
(continued)
B.1 Declare associated penetration flow path(s) incapable of automatic isolation.
CLINTON                          3.3-43a                      Amendment No. 95
AND B.2 Calculate DRAIN TIME.
Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
C.1 Place channel in trip.
1 hour (continued)  


RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43b Amendment No. 95 ACTIONS (continued)
CONDITION             REQUIRED ACTION           COMPLETION TIME D. As required by       D.1  Declare HPCS system      1 hour Required Action A.1       inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
and referenced in Table 3.3.5.2-1. OR D.2 Align the HPCS pump       1 hour suction to the suppression pool.
D.1 Declare HPCS system inoperable.
E. As required by       E.1  Restore channel to        24 hours Required Action A.1       OPERABLE status.
OR D.2 Align the HPCS pump suction to the suppression pool.
and referenced in Table 3.3.5.2-1.
1 hour 1 hour E. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
F. Required Action and F.1  Declare associated        Immediately associated               ECCS injection/spray Completion Time of       subsystem inoperable.
E.1 Restore channel to OPERABLE status.
Condition C, D, or E not met.
24 hours F. Required Action and associated Completion Time of Condition C, D, or E not met.
CLINTON                      3.3-43b                      Amendment No. 95
F.1 Declare associated ECCS injection/spray subsystem inoperable.
Immediately


RPV Water Inventory Control Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43c Amendment No. 9 5 SURVEILLANCE REQUIREMENTS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE                             FREQUENCY SR 3.3.5.2.1   Perform CHANNEL CHECK.                       In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2   Perform CHANNEL FUNCTIONAL TEST.             In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3   Perform LOGIC SYSTEM FUNCTIONAL TEST.         In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-43c                    Amendment No. 9    5
SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program  


RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 2)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43d Amendment No. 95 Table 3.3.5.2-1 (page 1 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE                 CONDITIONS MODES OR     REQUIRED   REFERENCED OTHER      CHANNELS     FROM SPECIFIED        PER     REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION           CONDITIONS     FUNCTION  ACTION A.1 REQUIREMENTS     VALUE
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
: 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
Subsystems
: a. Reactor                 4,5           4(a)         C   SR 3.3.5.2.1 494 psig Vessel Pressure -                                        SR 3.3.5.2.2 Low (Injection Permissive)
: a.
: b. LPCS Pump               4,5         1 per         E     SR 3.3.5.2.1 750 gpm Discharge Flow -                    pump(a)              SR 3.3.5.2.2 Low (Bypass)
Reactor Vessel Pressure -
: c. LPCI Pump A             4,5         1 per         E     SR 3.3.5.2.1 900 gpm Discharge Flow -                    pump(a)              SR 3.3.5.2.2 Low (Bypass)
Low (Injection Permissive) 4,5 4(a)
C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig
: b. LPCS Pump Discharge Flow -
Low (Bypass) 4,5 1 per pump(a)
E SR 3.3.5.2.1 SR 3.3.5.2.2 750 gpm
: c. LPCI Pump A Discharge Flow -
Low (Bypass) 4,5 1 per pump(a)
E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm
: 2. LPCI B and LPCI C Subsystems
: 2. LPCI B and LPCI C Subsystems
: a. Reactor Vessel           4,5         4(a)         C     SR 3.3.5.2.1   494 psig Pressure - Low                                            SR 3.3.5.2.2 (Injection Permissive)
: a. Reactor Vessel Pressure - Low (Injection Permissive) 4,5 4(a)
: b. LPCI Pump B             4,5         1 per         E     SR 3.3.5.2.1   900 gpm and LPCI Pump C                    pump(a)              SR 3.3.5.2.2 Discharge Flow -
C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig
Low (Bypass)
: b. LPCI Pump B and LPCI Pump C Discharge Flow -
(continued)
Low (Bypass) 4,5 1 per pump(a)
(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm (continued)
CLINTON                                    3.3-43d                        Amendment No.      95
(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."  


RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 2 of 2)
RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-44 Amendment No.
RPV Water Inventory Control Instrumentation APPLICABLE                 CONDITIONS MODES OR     REQUIRED   REFERENCED OTHER      CHANNELS       FROM SPECIFIED        PER       REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION           CONDITIONS     FUNCTION    ACTION A.1   REQUIREMENTS       VALUE
Table 3.3.5.2-1 (page 2 of 2)
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. High Pressure Core Spray (HPCS) System
: 3. High Pressure Core Spray (HPCS) System
: a. RCIC Storage Tank     4(b), 5(b)       2(a)         D     SR   3.3.5.2.1     3.0 inches Level - Low                                                SR   3.3.5.2.2
: a. RCIC Storage Tank Level - Low 4(b), 5(b) 2(a)
: b. HPCS Pump               4, 5         1(a)         E     SR   3.3.5.2.1     120 psig Discharge                                                  SR   3.3.5.2.2 Pressure - High (Bypass)
D SR 3.3.5.2.1 SR 3.3.5.2.2 3.0 inches
: c. HPCS System Flow         4, 5         1(a)         E     SR   3.3.5.2.1     500 gpm Rate - Low                                                SR   3.3.5.2.2 (Bypass)
: b. HPCS Pump Discharge Pressure - High (Bypass) 4, 5 1(a)
: 4. RHR System Isolation (c)
E SR 3.3.5.2.1 SR 3.3.5.2.2 120 psig
: a. Reactor Vessel                     2 in one       B     SR   3.3.5.2.1     8.3 inches Water Level -                        trip                SR   3.3.5.2.2 Low, Level 3                         system
: c. HPCS System Flow Rate - Low (Bypass) 4, 5 1(a)
: 5. Reactor Water Cleanup (RWCU) System Isolation (c)
E SR 3.3.5.2.1 SR 3.3.5.2.2 500 gpm
: a. Reactor Vessel                     2 in one       B     SR   3.3.5.2.1     -48.1 Water Level - Low                    trip                SR   3.3.5.2.2   inches Low, Level 2                        system (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
: 4. RHR System Isolation
: a. Reactor Vessel Water Level -
Low, Level 3 (c) 2 in one trip system B
SR 3.3.5.2.1 SR 3.3.5.2.2 8.3 inches
: 5. Reactor Water Cleanup (RWCU) System Isolation
: a. Reactor Vessel Water Level - Low Low, Level 2 (c) 2 in one trip system B
SR 3.3.5.2.1 SR 3.3.5.2.2  
-48.1 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."
(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.
(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.
(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
CLINTON                                      3.3-44                                  Amendment No.


RCIC System Instrumentation 3.3.5.3 3.3 INSTRUMENTATION 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.3     The RCIC System instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-45 Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.3 The RCIC System instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
APPLICABILITY:   MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
ACTIONS  
------------------------------------NOTE--------------------------------------
------------------------------------NOTE--------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                 REQUIRED ACTION         COMPLETION TIME A. One or more channels A.1   Enter the Condition       Immediately inoperable.                referenced in Table 3.3.5.3-1 for the channel.
CONDITION REQUIRED ACTION COMPLETION TIME A.
B. As required by       B.1  Declare RCIC System      1 hour from Required Action A.1         inoperable.              discovery of and referenced in                                     loss of RCIC Table 3.3.5.3-1.                                     initiation capability AND B.2   Place channel in         24 hours trip.
One or more channels inoperable.
C. As required by       C.1  Restore channel to        24 hours Required Action A.1         OPERABLE status.
A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel.
and referenced in Table 3.3.5.3-1.
Immediately B.
(continued)
As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
CLINTON                          3.3-45                        Amendment No. 95
B.1 Declare RCIC System inoperable.
AND B.2 Place channel in trip.
1 hour from discovery of loss of RCIC initiation capability 24 hours C.
As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
C.1 Restore channel to OPERABLE status.
24 hours (continued)  


RCIC System Instrumentation 3.3.5.3 ACTIONS (continued)
RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-46 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME D. As required by       D.1   ---------NOTE----------
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action A.1        Only applicable if and referenced in          RCIC pump suction is Table 3.3.5.3-1.          not aligned to the suppression pool.
As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
Declare RCIC System       1 hour from inoperable.               discovery of loss of RCIC initiation capability AND D.2.1 Place channel in         24 hours trip.
D.1  
OR D.2.2 Align RCIC pump           24 hours suction to the suppression pool.
---------NOTE----------
E. Required Action and   E.1  Declare RCIC System      Immediately associated Completion       inoperable.
Only applicable if RCIC pump suction is not aligned to the suppression pool.
Time of Condition B, C, or D not met.
Declare RCIC System inoperable.
CLINTON                        3.3-46                      Amendment No. 95
AND D.2.1 Place channel in trip.
OR D.2.2 Align RCIC pump suction to the suppression pool.
1 hour from discovery of loss of RCIC initiation capability 24 hours 24 hours E.
Required Action and associated Completion Time of Condition B, C, or D not met.
E.1 Declare RCIC System inoperable.
Immediately


RCIC System Instrumentation 3.3.5.3 SURVEILLANCE REQUIREMENTS
RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-47 Amendment No. 192 SURVEILLANCE REQUIREMENTS  
------------------------------------NOTES-------------------------------------
------------------------------------NOTES-------------------------------------
: 1. Refer to Table 3.3.5.3-1 to determine which SRs apply for each RCIC Function.
: 1. Refer to Table 3.3.5.3-1 to determine which SRs apply for each RCIC Function.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 5; and (b) for up to 6 hours for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 5; and (b) for up to 6 hours for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.
SURVEILLANCE                             FREQUENCY SR 3.3.5.3.1     Perform CHANNEL CHECK.                     In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.2     Perform CHANNEL FUNCTIONAL TEST.           In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.3     Calibrate the analog trip module.           In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.4     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.5     Perform LOGIC SYSTEM FUNCTIONAL TEST.       In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.6     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-47                      Amendment No. 192
SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.3 Calibrate the analog trip module.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.4 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.6 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program  


RCIC System Instrumentation 3.3.5.3 Table 3.3.5.3-1 (page 1 of 1)
RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-48 Amendment No. 169 Table 3.3.5.3-1 (page 1 of 1)
Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED    REFERENCED FROM CHANNELS PER  REQUIRED ACTION     SURVEILLANCE      ALLOWABLE FUNCTION              FUNCTION            A.1         REQUIREMENTS         VALUE
Reactor Core Isolation Cooling System Instrumentation FUNCTION REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Reactor Vessel Water             4               B         SR 3.3.5.3.1   -48.1 inches Level-Low Low, Level 2                                        SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.5 SR 3.3.5.3.6
: 1. Reactor Vessel Water Level-Low Low, Level 2 4
: 2. Reactor Vessel Water             2               C         SR 3.3.5.3.1   52.6 inches Level-High, Level 8                                          SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5
B SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.5 SR 3.3.5.3.6  
: 3. RCIC Storage Tank                 2               D         SR 3.3.5.3.1   3.0 inches Level-Low                                                    SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5
-48.1 inches
: 4. Suppression Pool Water           2               D         SR 3.3.5.3.1   -5 inches Level-High                                                    SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5
: 2. Reactor Vessel Water Level-High, Level 8 2
: 5. Manual Initiation               1                 C         SR 3.3.5.3.5   NA CLINTON                                      3.3-48                        Amendment No. 169
C SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5 52.6 inches
: 3. RCIC Storage Tank Level-Low 2
D SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5 3.0 inches
: 4. Suppression Pool Water Level-High 2
D SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5  
-5 inches
: 5. Manual Initiation 1
C SR 3.3.5.3.5 NA  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1     The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-49 Amendment No. 95 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1 The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:   According to Table 3.3.6.1-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.6.1-1.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION                   REQUIRED ACTION         COMPLETION TIME
CONDITION REQUIRED ACTION COMPLETION TIME  
-----------NOTE----------     A.1    Place one channel in  48 hours Only applicable to Main               affected Function in Steam Line (MSL) isolation           trip.
-----------NOTE----------
Functions.
Only applicable to Main Steam Line (MSL) isolation Functions.
A. One or more Functions with one channel inoperable.
A. One or more Functions with one channel inoperable.
-----------NOTE----------     B.1    Place one channel in  6 hours Only applicable to MSL               affected Function in isolation Functions.                  trip.
A.1 Place one channel in affected Function in trip.
B. One or more Functions with two channels inoperable.
48 hours
-----------NOTE----------     C.1    Restore two channels  1 hour Only applicable to MSL               in affected Function isolation Functions.                  to OPERABLE status.
-----------NOTE----------
Only applicable to MSL isolation Functions.
B.
One or more Functions with two channels inoperable.
B.1 Place one channel in affected Function in trip.
6 hours
-----------NOTE----------
Only applicable to MSL isolation Functions.
C. One or more Functions with three or more channels inoperable.
C. One or more Functions with three or more channels inoperable.
(continued)
C.1 Restore two channels in affected Function to OPERABLE status.
CLINTON                            3.3-49                      Amendment No. 95
1 hour (continued)


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-50 Amendment No. 95 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME
CONDITION REQUIRED ACTION COMPLETION TIME  
------------NOTE----------   D.1    Place channel in trip. 24 hours Not applicable to MSL isolation Functions.
------------NOTE----------
Not applicable to MSL isolation Functions.
D. One or more required channels inoperable.
D. One or more required channels inoperable.
------------NOTE---------   E.1    Restore isolation      1 hour Not applicable to MSL               capability.
D.1 Place channel in trip.
isolation Functions.
24 hours
------------NOTE---------
Not applicable to MSL isolation Functions.
E. One or more automatic Functions with isolation capability not maintained.
E. One or more automatic Functions with isolation capability not maintained.
F. Required Action and     F.1     Enter the Condition     Immediately associated Completion            referenced in Time of Condition A,            Table 3.3.6.1-1 for B, C, D, or E not                the channel.
E.1 Restore isolation capability.
met.
1 hour F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.
G. As required by           G.1    Isolate associated      12 hours Required Action F.1             MSL.
F.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.
and referenced in Table 3.3.6.1-1.         OR G.2.1   Be in MODE 3.           12 hours AND G.2.2   Be in MODE 4.           36 hours H. As required by           H.1     Be in MODE 2.           6 hours Required Action F.1 and referenced in Table 3.3.6.1-1.
Immediately G. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
I. As required by          I.1     Isolate the affected   1 hour Required Action F.1              penetration flow and referenced in                path(s).
G.1 Isolate associated MSL.
Table 3.3.6.1-1.
OR G.2.1 Be in MODE 3.
(continued)
AND G.2.2 Be in MODE 4.
CLINTON                          3.3-50                        Amendment No. 95
12 hours 12 hours 36 hours H. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
H.1 Be in MODE 2.
6 hours I. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
I.1 Isolate the affected penetration flow path(s).
1 hour (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-51 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME J. As required by         J.1    Isolate the affected    24 hours Required Action F.1             penetration flow and referenced in               path(s).
CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
Table 3.3.6.1-1.
J.1 Isolate the affected penetration flow path(s).
K. As required by         K.1    Be in MODE 3.          12 hours Required Action F.1 and referenced in       AND Table 3.3.6.1-1.
24 hours K. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
K.2    Be in MODE 4.          36 hours OR Required Action and associated Completion Time of Condition I or J not met.
OR Required Action and associated Completion Time of Condition I or J not met.
L. As required by         L.1    Declare associated      1 hour Required Action F.1             standby liquid and referenced in               control subsystem Table 3.3.6.1-1.               inoperable.
K.1 Be in MODE 3.
OR L.2     Isolate the Reactor     1 hour Water Cleanup System.
AND K.2 Be in MODE 4.
M. As required by         M.1    Initiate action to      Immediately Required Action F.1             restore channel to and referenced in               OPERABLE status.
12 hours 36 hours L. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
Table 3.3.6.1-1.
L.1 Declare associated standby liquid control subsystem inoperable.
OR M.2     Initiate action to     Immediately isolate the Residual Heat Removal (RHR)
OR L.2 Isolate the Reactor Water Cleanup System.
1 hour 1 hour M. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
M.1 Initiate action to restore channel to OPERABLE status.
OR M.2 Initiate action to isolate the Residual Heat Removal (RHR)
Shutdown Cooling System suction from the reactor vessel.
Shutdown Cooling System suction from the reactor vessel.
OR (continued)
OR Immediately Immediately (continued)  
CLINTON                          3.3-51                        Amendment No. 95


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION                   REQUIRED ACTION         COMPLETION TIME M.     (Continued)             M.3.1   Initiate action to       Immediately restore secondary containment to OPERABLE status.
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-52 Amendment No. 95 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M.
AND M.3.2   Initiate action to       Immediately restore one standby gas treatment (SGT) subsystem to OPERABLE status.
(Continued)
AND M.3.3   Initiate action to       Immediately restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.
M.3.1 Initiate action to restore secondary containment to OPERABLE status.
AND M.3.4   ---------NOTE-------
AND M.3.2 Initiate action to restore one standby gas treatment (SGT) subsystem to OPERABLE status.
AND M.3.3 Initiate action to restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.
AND M.3.4  
---------NOTE-------
Entry and exit is permissible under administrative control.
Entry and exit is permissible under administrative control.
Initiate action to close one door in the upper containment personnel   Immediately air lock.
Initiate action to close one door in the upper containment personnel air lock.
N. As required by         N.1    Isolate the affected    Immediately Required Action F.1             penetration flow and referenced in               path(s).
Immediately Immediately Immediately Immediately N.
Table 3.3.6.1-1.
As required by Required Action F.1 and referenced in Table 3.3.6.1-1.
OR N.2     Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
N.1 Isolate the affected penetration flow path(s).
(continued)
OR N.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
CLINTON                            3.3-52                        Amendment No. 95
Immediately Immediately (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-53 Amendment No. 192 SURVEILLANCE REQUIREMENTS  
------------------------------------NOTES------------------------------------
------------------------------------NOTES------------------------------------
: 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
: 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours, provided the associated Function maintains isolation capability.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours, provided the associated Function maintains isolation capability.
SURVEILLANCE                             FREQUENCY SR 3.3.6.1.1     Perform CHANNEL CHECK.                     In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2     Perform CHANNEL FUNCTIONAL TEST.           In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3     Calibrate the analog trip module.         In accordance with the Surveillance Frequency Control Program (continued)
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.
CLINTON                          3.3-53                      Amendment No. 192
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Calibrate the analog trip module.
In accordance with the Surveillance Frequency Control Program (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-54 Amendment No. 192 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                             FREQUENCY SR 3.3.6.1.4     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6     Perform LOGIC SYSTEM FUNCTIONAL TEST.     In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7     ---------------NOTE---------------------
SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7  
---------------NOTE---------------------
Channel sensors are excluded.
Channel sensors are excluded.
Verify the ISOLATION SYSTEM RESPONSE       In accordance TIME for the main steam isolation valves   with the is within limits.                         Surveillance Frequency Control Program SR 3.3.6.1.8     Perform CHANNEL CALIBRATION.               In accordance with the Surveillance Frequency Control Program CLINTON                          3.3-54                      Amendment No. 192
Verify the ISOLATION SYSTEM RESPONSE TIME for the main steam isolation valves is within limits.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-55 Amendment No. 169 Table 3.3.6.1-1 (page 1 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED    SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1   REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Main Steam Line Isolation
: 1. Main Steam Line Isolation
: a. Reactor Vessel Water         1,2,3         4         G     SR 3.3.6.1.1   -148.1 inches Level-Low Low Low,                                            SR 3.3.6.1.2 Level 1                                                      SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8
: a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4
: b. Main Steam Line                 1           4         H     SR 3.3.6.1.1   841 psig Pressure-Low                                                  SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8  
: c. Main Steam Line               1,2,3         4         G       SR 3.3.6.1.1   284 psid Flow-High                                                    SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
-148.1 inches
: d. Condenser Vacuum-Low         1,2(a),       4         G     SR 3.3.6.1.1   7.6 inches SR 3.3.6.1.2 Hg vacuum 3(a)                          SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. Main Steam Line Pressure-Low 1
: e. Main Steam Tunnel             1,2,3         4         G       SR 3.3.6.1.1   171&deg;F Temperature-High                                              SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
4 H
: f. Main Steam Line Turbine       1,2,3         4         G       SR 3.3.6.1.1 Modules 1-4 Building                                                      SR 3.3.6.1.2   142&deg;F, Temperature-High                                              SR 3.3.6.1.5  Module 5 SR 3.3.6.1.6   150&deg;F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 841 psig
: g. Manual Initiation             1,2,3         4         J       SR 3.3.6.1.6 NA (continued)
: c. Main Steam Line Flow-High 1,2,3 4
(a) With any turbine stop valve not closed.
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 284 psid
CLINTON                                    3.3-55                            Amendment No. 169
: d. Condenser Vacuum-Low 1,2(a),
3(a) 4 G
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7.6 inches Hg vacuum
: e. Main Steam Tunnel Temperature-High 1,2,3 4
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: f. Main Steam Line Turbine Building Temperature-High 1,2,3 4
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 Modules 1-4 142&deg;F, Module 5 150&deg;F
: g. Manual Initiation 1,2,3 4
J SR 3.3.6.1.6 NA (continued)
(a) With any turbine stop valve not closed.  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-56 Amendment No. 169 Table 3.3.6.1-1 (page 2 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. Primary Containment and Drywell Isolation
: 2. Primary Containment and Drywell Isolation
: a. Reactor Vessel Water       1,2,3         4(b)       K     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level 2                                      SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8
: a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4(b)
: b. Drywell Pressure-High       1,2,3         4(b)       K     SR 3.3.6.1.1   1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
: b. Drywell Pressure-High 1,2,3 4(b)
K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: c. Deleted
: c. Deleted
: d. Drywell Pressure-High       1,2,3         4(b)       I     SR 3.3.6.1.1   1.88 psig (ECCS Divisions 1                                          SR 3.3.6.1.2 and 2)                                                      SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: d. Drywell Pressure-High (ECCS Divisions 1 and 2) 1,2,3 4(b)
: e. Reactor Vessel Water       1,2,3         4         I     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level                                        SR 3.3.6.1.2 2 (HPCS NSPS Div 3                                          SR 3.3.6.1.3 and 4)                                                      SR 3.3.6.1.6 SR 3.3.6.1.8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: f. Drywell Pressure-High       1,2,3         4         I     SR 3.3.6.1.1   1.88 psig (HPCS NSPS Div 3 and                                        SR 3.3.6.1.2
: e. Reactor Vessel Water Level-Low Low, Level 2 (HPCS NSPS Div 3 and 4) 1,2,3 4
: 4)                                                          SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
(b) Also required to initiate the associated drywell isolation function.
-48.1 inches
CLINTON                                    3.3-56                            Amendment No. 169
: f. Drywell Pressure-High (HPCS NSPS Div 3 and
: 4) 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig (continued)
(b) Also required to initiate the associated drywell isolation function.  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-57 Amendment No. 169 Table 3.3.6.1-1 (page 3 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE                 CONDITIONS MODES OR     REQUIRED   REFERENCED OTHER      CHANNELS     FROM SPECIFIED        PER     REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION             CONDITIONS     FUNCTION  ACTION F.1 REQUIREMENTS     VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. Primary Containment and Drywell Isolation (continued)
: 2. Primary Containment and Drywell Isolation (continued)
: g. Containment Building         (c) 4         N     SR 3.3.6.1.1 500 mR/hr Fuel Transfer Pool                                            SR 3.3.6.1.2 Ventilation Plenum                                            SR 3.3.6.1.5 Radiation-High                                                SR 3.3.6.1.6
: g. Containment Building Fuel Transfer Pool Ventilation Plenum Radiation-High (c) 4 N
: h. Containment Building       1,2,3         4(b)         I     SR 3.3.6.1.1 400 mR/hr Exhaust                                                        SR 3.3.6.1.2 Radiation-High                                                SR 3.3.6.1.5 SR 3.3.6.1.6 (c) 4         N     SR 3.3.6.1.1 400 mR/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 500 mR/hr
: i. Containment Building       1,2,3         4(b)         I     SR 3.3.6.1.1 400 mR/hr Continuous                                                    SR 3.3.6.1.2 Containment Purge                                              SR 3.3.6.1.5 (CCP) Exhaust                                                  SR 3.3.6.1.6 Radiation-High (c) 4         N     SR 3.3.6.1.1 400 mR/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
: h. Containment Building Exhaust Radiation-High 1,2,3 4(b)
: j. Reactor Vessel Water       1,2,3         4(b)         I     SR 3.3.6.1.1 -148.1 inches Level-Low Low Low,                                            SR 3.3.6.1.2 Level 1                                                        SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 (d)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c) 4 N
: k. Containment Pressure-                       2         I     SR 3.3.6.1.1 3.0 psid High                                                          SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr
: l. Manual Initiation           1,2,3         2(b)         J     SR 3.3.6.1.6 NA (c) 2         N     SR 3.3.6.1.6 NA (continued)
: i. Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3 4(b)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c) 4 N
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr
: j. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4(b)
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-148.1 inches
: k. Containment Pressure-High (d) 2 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 3.0 psid
: l. Manual Initiation 1,2,3 2(b)
J SR 3.3.6.1.6 NA (c) 2 N
SR 3.3.6.1.6 NA (continued)
(b) Also required to initiate the associated drywell isolation function.
(b) Also required to initiate the associated drywell isolation function.
(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(d) MODES 1, 2, and 3 with the associated PCIVs not closed.
(d) MODES 1, 2, and 3 with the associated PCIVs not closed.  
CLINTON                                    3.3-57                            Amendment No. 169


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-58 Amendment No. 169 Table 3.3.6.1-1 (page 4 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED  SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. Reactor Core Isolation Cooling (RCIC) System Isolation
: 3. Reactor Core Isolation Cooling (RCIC) System Isolation
: a. Auxiliary Building           1,2,3         2         I     SR 3.3.6.1.1   118.5 inches RCIC Steam Line                                            SR 3.3.6.1.2 water Flow-High                                                  SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: a. Auxiliary Building RCIC Steam Line Flow-High 1,2,3 2
: b. RCIC Steam Line             1,2,3         2         I     SR 3.3.6.1.2   13 seconds Flow-High,                                                  SR 3.3.6.1.5 Time Delay                                                  SR 3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 118.5 inches water
: c. RCIC Steam Supply Line       1,2,3         2         I     SR 3.3.6.1.1   52 psig Pressure-Low                                                SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. RCIC Steam Line Flow-High, Time Delay 1,2,3 2
: d. RCIC Turbine Exhaust         1,2,3         4         I     SR 3.3.6.1.1   20 psig Diaphragm                                                  SR 3.3.6.1.2 Pressure-High                                              SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 13 seconds
: e. RCIC Equipment Room         1,2,3         2         I     SR 3.3.6.1.1   207&deg;F Ambient                                                    SR 3.3.6.1.2 Temperature-High                                            SR 3.3.6.1.5 SR 3.3.6.1.6
: c. RCIC Steam Supply Line Pressure-Low 1,2,3 2
: f. Main Steam Line Tunnel       1,2,3         2         I     SR   3.3.6.1.1 171&deg;F Ambient                                                    SR   3.3.6.1.2 Temperature-High                                            SR   3.3.6.1.5 SR   3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 52 psig
: g. Main Steam Line Tunnel       1,2,3         2         I     SR 3.3.6.1.2   28 minutes Temperature Timer                                          SR   3.3.6.1.5 SR   3.3.6.1.6
: d. RCIC Turbine Exhaust Diaphragm Pressure-High 1,2,3 4
: h. Reactor Vessel Water         1,2,3         4         I     SR 3.3.6.1.1   -48.1 inches Level-Low Low, Level 2                                      SR   3.3.6.1.2 SR   3.3.6.1.3 SR   3.3.6.1.6 SR   3.3.6.1.8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 20 psig
: i. Drywell RCIC Steam           1,2,3         2         I     SR 3.3.6.1.1   188 inches Line Flow - High                                            SR   3.3.6.1.2 water SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6 (continued)
: e. RCIC Equipment Room Ambient Temperature-High 1,2,3 2
CLINTON                                    3.3-58                            Amendment No. 169
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 207&deg;F
: f. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: g. Main Steam Line Tunnel Temperature Timer 1,2,3 2
I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 28 minutes
: h. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
: i. Drywell RCIC Steam Line Flow - High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188 inches water (continued)  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-59 Amendment No. 169 Table 3.3.6.1-1 (page 5 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE             CONDITIONS MODES OR   REQUIRED REFERENCED OTHER    CHANNELS     FROM SPECIFIED      PER     REQUIRED  SURVEILLANCE      ALLOWABLE FUNCTION             CONDITIONS   FUNCTION  ACTION F.1 REQUIREMENTS       VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. RCIC System Isolation (continued)
: 3.
: j. Drywell Pressure - High       1,2,3       2         I     SR   3.3.6.1.1 1.88 psig SR   3.3.6.1.2 SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6
RCIC System Isolation (continued)
: k. Manual Initiation             1,2,3       1         J     SR   3.3.6.1.6 NA
: j. Drywell Pressure - High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: k. Manual Initiation 1,2,3 1
J SR 3.3.6.1.6 NA
: 4. Reactor Water Cleanup (RWCU) System Isolation
: 4. Reactor Water Cleanup (RWCU) System Isolation
: a. Differential Flow -           1,2,3       2         I     SR   3.3.6.1.1 66.1 gpm High                                                        SR   3.3.6.1.2 SR   3.3.6.1.6 SR   3.3.6.1.8
: a. Differential Flow -
: b. Differential Flow-Timer       1,2,3       2         I     SR   3.3.6.1.2 47 seconds SR   3.3.6.1.4 SR   3.3.6.1.6
High 1,2,3 2
: c. RWCU Heat Exchanger           1,2,3     2 per       I     SR   3.3.6.1.1 205&deg;F Equipment Room                            room              SR   3.3.6.1.2 Temperature-High                                            SR   3.3.6.1.5 SR   3.3.6.1.6
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8 66.1 gpm
: d. RWCU Pump Rooms               1,2,3     2 per       I     SR   3.3.6.1.1 202&deg;F Temperature-High                          room              SR   3.3.6.1.2 SR   3.3.6.1.5 SR   3.3.6.1.6
: b. Differential Flow-Timer 1,2,3 2
: e. Main Steam Line Tunnel       1,2,3       2         I     SR   3.3.6.1.1 171&deg;F Ambient Temperature-                                        SR   3.3.6.1.2 High                                                        SR   3.3.6.1.5 SR   3.3.6.1.6
I SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 47 seconds
: f. Reactor Vessel Water         1,2,3       4         I     SR   3.3.6.1.1 -48.1 inches Level-Low Low,                                              SR   3.3.6.1.2 Level 2                                                    SR   3.3.6.1.3 SR   3.3.6.1.6 SR   3.3.6.1.8
: c. RWCU Heat Exchanger Equipment Room Temperature-High 1,2,3 2 per room I
: g. Standby Liquid Control       1,2,3       2         L     SR   3.3.6.1.6 NA System Initiation
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 205&deg;F
: h. Manual Initiation             1,2,3         2         J     SR   3.3.6.1.6 NA (c) 2        N    SR   3.3.6.1.6 NA (continued)
: d. RWCU Pump Rooms Temperature-High 1,2,3 2 per room I
(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 202&deg;F
CLINTON                                    3.3-59                            Amendment No. 169
: e. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171&deg;F
: f. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
-48.1 inches
: g. Standby Liquid Control System Initiation 1,2,3 2
L SR 3.3.6.1.6 NA
: h. Manual Initiation 1,2,3 (c) 2 2
J N
SR 3.3.6.1.6 SR 3.3.6.1.6 NA NA (continued)
(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-60 Amendment No. 169 Table 3.3.6.1-1 (page 6 of 6)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE                 CONDITIONS MODES OR                 REFERENCED OTHER       REQUIRED       FROM SPECIFIED    CHANNELS PER   REQUIRED  SURVEILLANCE    ALLOWABLE FUNCTION           CONDITIONS     FUNCTION    ACTION F.1 REQUIREMENTS     VALUE
Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. RHR System Isolation
: 5. RHR System Isolation
: a. RHR Heat Exchanger         1,2,3     2 per room       I     SR 3.3.6.1.1 160&deg;F Ambient                                                        SR 3.3.6.1.2 Temperature-High                                              SR 3.3.6.1.5 SR 3.3.6.1.6
: a. RHR Heat Exchanger Ambient Temperature-High 1,2,3 2 per room I
: b. Reactor Vessel Water       1,2,3(e)         4           I     SR 3.3.6.1.1 8.3 inches Level - Low, Level 3                                          SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 160&deg;F
: c. Reactor Vessel Water         3(f)           4           M     SR 3.3.6.1.1 8.3 inches Level - Low, Level 3                                          SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: b. Reactor Vessel Water Level - Low, Level 3 1,2,3(e) 4 I
: d. Reactor Vessel Water       1,2,3           4           I     SR 3.3.6.1.1 -148.1 Level - Low Low Low,                                          SR 3.3.6.1.2 inches Level 1                                                        SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches
: e. Reactor Vessel             1,2,3           4           I     SR 3.3.6.1.1 113 psig Pressure-High                                                  SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
: c. Reactor Vessel Water Level - Low, Level 3 3(f) 4 M
: f. Drywell Pressure-High       1,2,3           8           I     SR 3.3.6.1.1 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches
: g. Manual Initiation           1,2,3           2           J     SR 3.3.6.1.6 NA (e) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.
: d. Reactor Vessel Water Level - Low Low Low, Level 1 1,2,3 4
(f) With reactor steam dome pressure less than the RHR cut in permissive pressure.
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8  
CLINTON                                    3.3-60                            Amendment No. 169
-148.1 inches
: e. Reactor Vessel Pressure-High 1,2,3 4
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 113 psig
: f. Drywell Pressure-High 1,2,3 8
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig
: g. Manual Initiation 1,2,3 2
J SR 3.3.6.1.6 NA (e) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.
(f) With reactor steam dome pressure less than the RHR cut in permissive pressure.  


Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation 3.3.6.2 CLINTON 3.3-64 Amendment No. 169 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation APPLICABLE MODES OR     REQUIRED OTHER      CHANNELS SPECIFIED      PER TRIP SURVEILLANCE         ALLOWABLE FUNCTION              CONDITIONS      SYSTEM  REQUIREMENTS          VALUE
Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Reactor Vessel Water             1,2,3           2   SR 3.3.6.2.1   -48.1 inches Level-Low Low, Level 2                                SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6
: 1.
: 2. Drywell Pressure-High           1,2,3           2     SR 3.3.6.2.1   1.88 psig SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 (a)
Reactor Vessel Water Level-Low Low, Level 2 1,2,3 2
: 3. Containment Building Fuel                       2   SR 3.3.6.2.1   500 mR/hr Transfer Pool Ventilation                            SR 3.3.6.2.2 Plenum Exhaust                                        SR 3.3.6.2.4 Radiation-High                                        SR 3.3.6.2.5
SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6  
: 4. Containment Building           1,2,3,(a)         2   SR 3.3.6.2.1   400 mR/hr Exhaust Radiation-High                                SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5
-48.1 inches
: 5. Containment Building           1,2,3,(a)         2   SR 3.3.6.2.1   400 mR/hr Continuous Containment                                SR 3.3.6.2.2 Purge (CCP) Exhaust                                  SR 3.3.6.2.4 Radiation-High                                        SR 3.3.6.2.5
: 2.
: 6. Fuel Building Exhaust         1,2,3,(b)         2   SR 3.3.6.2.1   17 mR/hr Radiation-High                                        SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5
Drywell Pressure-High 1,2,3 2
: 7. Manual Initiation             1,2,3,(a)         1   SR 3.3.6.2.5 NA (a) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 1.88 psig
(b) During movement of recently irradiated fuel assemblies in the fuel building.
: 3.
CLINTON                                      3.3-64                        Amendment No. 169
Containment Building Fuel Transfer Pool Ventilation Plenum Exhaust Radiation-High (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 500 mR/hr
: 4.
Containment Building Exhaust Radiation-High 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr
: 5.
Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr
: 6.
Fuel Building Exhaust Radiation-High 1,2,3,(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 17 mR/hr
: 7.
Manual Initiation 1,2,3,(a) 1 SR 3.3.6.2.5 NA (a) During movement of recently irradiated fuel assemblies in the primary or secondary containment.
(b) During movement of recently irradiated fuel assemblies in the fuel building.  


Control Room Ventilation System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)
Control Room Ventilation System Instrumentation 3.3.7.1 CLINTON 3.3-77 Amendment No. 152 Table 3.3.7.1-1 (page 1 of 1)
Control Room Ventilation System Instrumentation APPLICABLE MODES OR OTHER         REQUIRED SPECIFIED        CHANNELS PER   SURVEILLANCE        ALLOWABLE FUNCTION        CONDITIONS        TRIP SYSTEM   REQUIREMENTS         VALUE
Control Room Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Control           1,2,3,(a)         1/Intake   SR 3.3.7.1.1   26 mR/hr Room Air                                        SR 3.3.7.1.2 Intake                                          SR 3.3.7.1.3 Radiation Monitors (a)   During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.
: 1. Control Room Air Intake Radiation Monitors 1,2,3,(a) 1/Intake SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 26 mR/hr (a)
CLINTON                                    3.3-77                            Amendment No. 152
During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.  


ECCS Operating 3.5.1 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
ECCS Operating 3.5.1 CLINTON 3.5-1 Amendment No. 163 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.1   ECCS Operating LCO 3.5.1         Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/
SYSTEM 3.5.1 ECCS Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/
relief valves shall be OPERABLE.
relief valves shall be OPERABLE.  
                  ----------------------------NOTE----------------------------
----------------------------NOTE----------------------------
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
APPLICABILITY:     MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.4.b is not applicable to HPCS.
LCO 3.0.4.b is not applicable to HPCS.
CONDITION                   REQUIRED ACTION         COMPLETION TIME A. One low pressure ECCS     A.1     Restore low pressure   7 days injection/spray                    ECCS injection/spray subsystem inoperable.              subsystem to OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.
B. High Pressure Core       B.1     Verify by             1 hour Spray (HPCS) System                administrative means inoperable.                        RCIC System is OPERABLE when RCIC is required to be OPERABLE.
A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.
AND B.2     Restore HPCS System   14 days to OPERABLE status.
7 days B. High Pressure Core Spray (HPCS) System inoperable.
(continued)
B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.
CLINTON                                3.5-1                  Amendment No. 163
AND B.2 Restore HPCS System to OPERABLE status.
1 hour 14 days (continued)  


RPV Water Inventory Control 3.5.2 3.5   EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
RPV Water Inventory Control 3.5.2 CLINTON 3.5-6 Amendment No. 133 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.2   RPV Water Inventory Control LCO 3.5.2       DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
SYSTEM 3.5.2 RPV Water Inventory Control LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
AND One ECCS injection/spray subsystem shall be OPERABLE.
AND One ECCS injection/spray subsystem shall be OPERABLE.  
                  ----------------------------NOTE----------------------------
----------------------------NOTE----------------------------
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.
APPLICABILITY:   MODES 4 and 5.
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION           COMPLETION TIME A. Required ECCS           A.1     Restore required ECCS   4 hours injection/spray                  injection/spray subsystem inoperable.            subsystem to OPERABLE status.
MODES 4 and 5.
B. Required Action and     B.1     Initiate action to     Immediately associated Completion            establish a method of Time of Condition A              water injection not met.                          capable of operating without offsite electrical power.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS injection/spray subsystem inoperable.
(continued)
A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.
CLINTON                              3.5-6                    Amendment No. 133
4 hours B. Required Action and associated Completion Time of Condition A not met.
B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.
Immediately (continued)  


RPV Water Inventory Control 3.5.2 ACTIONS (continued)
RPV Water Inventory Control 3.5.2 CLINTON 3.5-7 Amendment No. 133 ACTIONS (continued)
CONDITION           REQUIRED ACTION         COMPLETION TIME C. DRAIN TIME < 36 hours C.1 Verify secondary         4 hours and  8 hours.            containment boundary is capable of being established in less than the DRAIN TIME.
CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours and 8 hours.
AND C.2 Verify each secondary   4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
C.1 Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.
AND C.3 Verify one standby gas   4 hours treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
(continued)
AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
CLINTON                        3.5-7                  Amendment No. 133
4 hours 4 hours 4 hours (continued)


RPV Water Inventory Control 3.5.2 ACTIONS (continued)
RPV Water Inventory Control 3.5.2 CLINTON 3.5-8 Amendment No. 133 ACTIONS (continued)
CONDITION           REQUIRED ACTION           COMPLETION TIME D. DRAIN TIME < 8 hours. D.1 ------- NOTE --------
CONDITION REQUIRED ACTION COMPLETION TIME D. DRAIN TIME < 8 hours.
D.1  
------- NOTE --------
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
Initiate action to     Immediately establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.
AND D.2 Initiate action to     Immediately establish secondary containment boundary.
AND D.2 Initiate action to establish secondary containment boundary.
AND D.3 Initiate action to     Immediately isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
AND D.4 Initiate action to     Immediately verify one standby gas treatment subsystem is capable of being placed in operation.
AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
(continued)
Immediately Immediately Immediately Immediately (continued)  
CLINTON                        3.5-8                    Amendment No. 133


RPV Water Inventory Control 3.5.2 ACTIONS (continued)
RPV Water Inventory Control 3.5.2 CLINTON 3.5-9 Amendment No. 204 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME E. Required Action and     E.1      Initiate action to      Immediately associated Completion             restore DRAIN TIME to Time of Condition C               36 hours.
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.
or D not met.
OR DRAIN TIME < 1 hour.
OR DRAIN TIME < 1 hour.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.5.2.1   Verify DRAIN TIME 36 hours.                   In accordance with the Surveillance Frequency Control Program SR 3.5.2.2   Verify, for a required low pressure ECCS       In accordance injection/spray subsystem, the suppression     with the pool water level is 12 ft 8 inches.           Surveillance Frequency Control Program SR 3.5.2.3   Verify, for a required High Pressure Core       In accordance Spray (HPCS) System, the:                       with the Surveillance
E.1 Initiate action to restore DRAIN TIME to 36 hours.
: a. Suppression pool water level is           Frequency 12 ft 8 inches; or                       Control Program
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours.
: b. RCIC storage tank available water volume is 125,000 gal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.2 Verify, for a required low pressure ECCS injection/spray subsystem, the suppression pool water level is 12 ft 8 inches.
SR 3.5.2.4   Verify, for the required ECCS                   In accordance injection/spray subsystem, locations           with the susceptible to gas accumulation are             Surveillance sufficiently filled with water.                 Frequency Control Program (continued)
In accordance with the Surveillance Frequency Control Program SR 3.5.2.3 Verify, for a required High Pressure Core Spray (HPCS) System, the:
CLINTON                              3.5-9                    Amendment No. 204
: a.
Suppression pool water level is 12 ft 8 inches; or
: b.
RCIC storage tank available water volume is 125,000 gal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program (continued)  


RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS   (continued)
RPV Water Inventory Control 3.5.2 CLINTON 3.5-10 Amendment No. 204 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                             FREQUENCY SR 3.5.2.5   --------------------NOTE-------------------
SURVEILLANCE FREQUENCY SR 3.5.2.5  
--------------------NOTE-------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify, for the required ECCS                 In accordance injection/spray subsystem, each manual,       with the power operated, and automatic valve in the     Surveillance flow path, that is not locked, sealed, or     Frequency otherwise secured in position, is in the       Control Program correct position.
Verify, for the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.6   Operate the required ECCS injection/spray     In accordance subsystem through the recirculation line       with the for 10 minutes.                             Surveillance Frequency Control Program SR 3.5.2.7     Verify each valve credited for               In accordance automatically isolating a penetration flow   with the path actuates to the isolation position on   Surveillance an actual or simulated isolation signal.     Frequency Control Program SR 3.5.2.8   -------------------NOTE--------------------
In accordance with the Surveillance Frequency Control Program SR 3.5.2.6 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.8  
-------------------NOTE--------------------
Vessel injection/spray may be excluded.
Vessel injection/spray may be excluded.
Verify the required ECCS injection/spray       In Accordance subsystem can be manually operated.           with the Surveillance Frequency Control Program CLINTON                              3.5-10                  Amendment No. 204
Verify the required ECCS injection/spray subsystem can be manually operated.
In Accordance with the Surveillance Frequency Control Program  


RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
RCIC System 3.5.3 CLINTON 3.5-11 Amendment No. XXX 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.3   RCIC System LCO 3.5.3       The RCIC System shall be OPERABLE.
SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.
APPLICABILITY:   MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.4.b is not applicable to RCIC.
LCO 3.0.4.b is not applicable to RCIC.
CONDITION                   REQUIRED ACTION       COMPLETION TIME A. RCIC System               A.1     Verify by             1 hour inoperable.                        administrative means High Pressure Core Spray System is OPERABLE.
CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.
AND A.2     Restore RCIC System   14 days to OPERABLE status.
A.1 Verify by administrative means High Pressure Core Spray System is OPERABLE.
B. Required Action and       B.1     Be in MODE 3.         12 hours associated Completion Time not met.            AND B.2     Reduce reactor steam 36 hours dome pressure to 150 psig.
AND A.2 Restore RCIC System to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                           FREQUENCY SR 3.5.3.1     Verify the RCIC System locations             In accordance susceptible to gas accumulation are           with the sufficiently filled with water.               Surveillance Frequency Control Program (continued)
1 hour 14 days B. Required Action and associated Completion Time not met.
CLINTON                              3.5-11                  Amendment No. XXX
B.1 Be in MODE 3.
AND B.2 Reduce reactor steam dome pressure to 150 psig.
12 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program (continued)  


RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS   (continued)
RCIC System 3.5.3 CLINTON 3.5-12 Amendment No. XXX SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                           FREQUENCY SR 3.5.3.2   -------------------NOTE--------------------
SURVEILLANCE FREQUENCY SR 3.5.3.2  
-------------------NOTE--------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify each RCIC System manual, power       In accordance operated, and automatic valve in the flow   with the path, that is not locked, sealed, or         Surveillance otherwise secured in position, is in the     Frequency correct position.                           Control Program SR 3.5.3.3   -------------------NOTE--------------------
Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.3  
-------------------NOTE--------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with RCIC steam supply pressure     In accordance 1045 psig and 920 psig, the RCIC pump   with the can develop a flow rate 600 gpm against a Surveillance system head corresponding to reactor         Frequency pressure.                                   Control Program SR 3.5.3.4   -------------------NOTE--------------------
Verify, with RCIC steam supply pressure 1045 psig and 920 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.4  
-------------------NOTE--------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with RCIC steam supply pressure     In accordance 150 psig and 135 psig, the RCIC pump     with the can develop a flow rate 600 gpm against a Surveillance system head corresponding to reactor         Frequency pressure.                                   Control Program SR 3.5.3.5   -------------------NOTE--------------------
Verify, with RCIC steam supply pressure 150 psig and 135 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.5  
-------------------NOTE--------------------
Vessel injection may be excluded.
Vessel injection may be excluded.
Verify the RCIC System actuates on an       In accordance actual or simulated automatic initiation     with the signal.                                      Surveillance Frequency Control Program CLINTON                              3.5-12                Amendment No. XXX
Verify the RCIC System actuates on an actual or simulated automatic initiation signal.
In accordance with the Surveillance Frequency Control Program  


Primary Containment Air Locks 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2     Each primary containment air lock shall be OPERABLE.
Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-3 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 Each primary containment air lock shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3,
APPLICABILITY:
                -----------------------NOTE------------------------------
MODES 1, 2, and 3,  
-----------------------NOTE------------------------------
The following Applicability applies only to the upper containment personnel air lock.
The following Applicability applies only to the upper containment personnel air lock.
During movement of recently irradiated fuel assemblies in the primary or secondary containment.
During movement of recently irradiated fuel assemblies in the primary or secondary containment.
ACTIONS
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Entry and exit is permissible to perform repairs of the affected air lock components.
: 1. Entry and exit is permissible to perform repairs of the affected air lock components.
: 2. Separate Condition entry is allowed for each air lock.
: 2. Separate Condition entry is allowed for each air lock.
: 3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
(continued)
(continued)  
CLINTON                          3.6-3                      Amendment No. 147


Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)
Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-7 Amendment No. 147 ACTIONS (continued)
CONDITION               REQUIRED ACTION         COMPLETION TIME E. Required Action and     ------------NOTE------------
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition A, B, or C not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.
associated Completion  LCO 3.0.3 is not applicable.
------------NOTE------------
Time of Condition A,  ----------------------------
LCO 3.0.3 is not applicable.
B, or C not met during movement of recently  E.1   Suspend movement of       Immediately irradiated fuel              recently irradiated assemblies in the            fuel assemblies in the primary or secondary        primary and secondary containment.                containment.
E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
CLINTON                        3.6-7                      Amendment No. 147
Immediately


PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
PCIVs 3.6.1.3 CLINTON 3.6-9 Amendment No. 158 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
LCO 3.6.1.3     Each PCIV shall be OPERABLE.
LCO 3.6.1.3 Each PCIV shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3,
APPLICABILITY:
                -----------------------NOTE------------------------------
MODES 1, 2, and 3,  
-----------------------NOTE------------------------------
The following Applicability applies only to secondary containment bypass leakage isolation valves.
The following Applicability applies only to secondary containment bypass leakage isolation valves.
During movement of recently irradiated fuel assemblies in the primary or secondary containment.
During movement of recently irradiated fuel assemblies in the primary or secondary containment.
ACTIONS
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
Line 1,505: Line 1,977:
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
: 4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
: 5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.
: 5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.
(continued)
(continued)  
CLINTON                          3.6-9                      Amendment No. 158


PCIVs 3.6.1.3 ACTIONS CONDITION                 REQUIRED ACTION     COMPLETION TIME D. (continued)           D.3   Perform SR 3.6.1.3.5 Once per 92 for the resilient     days seal purge valves closed to comply with Required Action D.1.
PCIVs 3.6.1.3 CLINTON 3.6-14 Amendment No. 147 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)
E. Required Action and   E.1  Be in MODE 3.        12 hours associated Completion Time of Condition A, AND B, C, or D not met in MODE 1, 2, or 3.     E.2   Be in MODE 4.         36 hours F. Required Action and   F.1   --------NOTE---------
D.3 Perform SR 3.6.1.3.5 for the resilient seal purge valves closed to comply with Required Action D.1.
associated Completion      LCO 3.0.3 is not Time of Condition A,        applicable.
Once per 92 days E. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.
B, C, or D not met          ---------------------
E.1 Be in MODE 3.
for PCIV(s) required to be OPERABLE during      Suspend movement of  Immediately movement of recently        recently irradiated irradiated fuel            fuel assemblies in assemblies in the          primary and secondary primary or secondary        containment.
AND E.2 Be in MODE 4.
containment.
12 hours 36 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during movement of recently irradiated fuel assemblies in the primary or secondary containment.
CLINTON                        3.6-14                  Amendment No. 147
F.1  
--------NOTE---------
LCO 3.0.3 is not applicable.
Suspend movement of recently irradiated fuel assemblies in primary and secondary containment.
Immediately


Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1     The secondary containment shall be OPERABLE.
Secondary Containment 3.6.4.1 CLINTON 3.6-43 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
APPLICABILITY:
ACTIONS CONDITION                   REQUIRED ACTION         COMPLETION TIME A. Secondary containment   A.1    Restore secondary      4 hours inoperable in MODE 1,           containment to 2, or 3.                       OPERABLE status.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
B. Required Action and     ------------NOTE------------
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
associated Completion  LCO 3.0.4.a is not Time of Condition A    applicable when entering not met.                MODE 3.
Secondary containment inoperable in MODE 1, 2, or 3.
B.1     Be in MODE 3.           12 hours (continued)
A.1 Restore secondary containment to OPERABLE status.
CLINTON                          3.6-43                      Amendment No. 187
4 hours B.
Required Action and associated Completion Time of Condition A not met.
------------NOTE------------
LCO 3.0.4.a is not applicable when entering MODE 3.
B.1 Be in MODE 3.
12 hours (continued)  


Secondary Containment 3.6.4.1 ACTIONS (continued)
Secondary Containment 3.6.4.1 CLINTON 3.6-44 Amendment No. 192 ACTIONS (continued)
CONDITION                   REQUIRED ACTION         COMPLETION TIME C. Secondary containment     C.1     --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment.
inoperable during                LCO 3.0.3 is not movement of recently            applicable.
C.1  
irradiated fuel                  ---------------------
--------NOTE---------
assemblies in the primary or secondary            Suspend movement of     Immediately containment.                    recently irradiated fuel assemblies in the primary and secondary containment.
LCO 3.0.3 is not applicable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.6.4.1.1   Verify secondary containment vacuum is       In accordance 0.25 inch of vacuum water gauge.           with the Surveillance Frequency Control Program SR 3.6.4.1.2   Verify all secondary containment             In accordance equipment hatches are closed and sealed. with the Surveillance Frequency Control Program (continued)
Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
CLINTON                          3.6-44                      Amendment No. 192
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.
In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.
In accordance with the Surveillance Frequency Control Program (continued)  


SCIDs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)
SCIDs 3.6.4.2 CLINTON 3.6-47 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)
LCO 3.6.4.2     Each SCID shall be OPERABLE.
LCO 3.6.4.2 Each SCID shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
APPLICABILITY:
ACTIONS
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
ACTIONS  
-------------------------------------NOTES------------------------------------
-------------------------------------NOTES------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 2. Separate Condition entry is allowed for each penetration flow path.
: 2. Separate Condition entry is allowed for each penetration flow path.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.
(continued)
(continued)  
CLINTON                          3.6-47                      Amendment No. 147


SCIDs 3.6.4.2 ACTIONS (continued)
SCIDs 3.6.4.2 CLINTON 3.6-49 Amendment No. 147 ACTIONS (continued)
CONDITION                 REQUIRED ACTION       COMPLETION TIME D. Required Action and     D.1     --------NOTE---------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.
associated Completion          LCO 3.0.3 is not Time of Condition A or        applicable.
D.1  
B not met during              ---------------------
--------NOTE---------
movement of recently irradiated fuel                Suspend movement of   Immediately assemblies in the              recently irradiated primary or secondary          fuel assemblies in the containment.                  primary and secondary containment.
LCO 3.0.3 is not applicable.
CLINTON                        3.6-49                    Amendment No. 147
Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
Immediately


SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3     Two SGT subsystems shall be OPERABLE.
SGT System 3.6.4.3 CLINTON 3.6-51 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION         COMPLETION TIME A. One SGT subsystem       A.1   Restore SGT subsystem   7 days inoperable.                    to OPERABLE status.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.
B. Required Action and     ------------NOTE------------
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.
associated Completion    LCO 3.0.4.a is not Time of Condition A      applicable when entering not met in MODE 1, 2,    MODE 3.
A.1 Restore SGT subsystem to OPERABLE status.
or 3.                    ----------------------------
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
B.1   Be in MODE 3.           12 hours (continued)
------------NOTE------------
CLINTON                          3.6-51                      Amendment No. 187
LCO 3.0.4.a is not applicable when entering MODE 3.
B.1 Be in MODE 3.
12 hours (continued)  


SGT System 3.6.4.3 ACTIONS (continued)
SGT System 3.6.4.3 CLINTON 3.6-52 Amendment No. 187 ACTIONS (continued)
CONDITION                 REQUIRED ACTION       COMPLETION TIME C. Required Action and     -------------NOTE------------
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.
associated Completion  LCO 3.0.3 is not applicable.
-------------NOTE------------
Time of Condition A    -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of recently    C.1     Place OPERABLE SGT     Immediately irradiated fuel                subsystem in assemblies in the              operation.
C.1 Place OPERABLE SGT subsystem in operation.
primary or secondary containment.            OR C.2     Suspend movement of   Immediately recently irradiated fuel assemblies in the primary and secondary containment.
OR C.2 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
D. Two SGT subsystems   ------------NOTE------------
Immediately Immediately D.
inoperable in MODE 1, LCO 3.0.4.a is not 2, or 3.              applicable when entering MODE 3.
Two SGT subsystems inoperable in MODE 1, 2, or 3.
D.1     Be in MODE 3.         12 hours (continued)
------------NOTE------------
CLINTON                        3.6-52                    Amendment No. 187
LCO 3.0.4.a is not applicable when entering MODE 3.
D.1 Be in MODE 3.
12 hours (continued)  


SGT System 3.6.4.3 ACTIONS (continued)
SGT System 3.6.4.3 CLINTON 3.6-53 Amendment No. 201 ACTIONS (continued)
CONDITION                   REQUIRED ACTION       COMPLETION TIME E. Two SGT subsystems       E.1    Suspend movement of    Immediately inoperable during               recently irradiated movement of recently             fuel assemblies in the irradiated fuel                 primary and secondary assemblies in the               containment.
CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment.
primary or secondary containment.
E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                           FREQUENCY SR 3.6.4.3.1     Operate each SGT subsystem for           In accordance 15 continuous minutes with             with the heaters operating.                       Surveillance Frequency Control Program SR 3.6.4.3.2     Perform required SGT filter testing in   In accordance accordance with the Ventilation Filter   with the VFTP Testing Program (VFTP).
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes with heaters operating.
SR 3.6.4.3.3     Verify each SGT subsystem actuates on an In accordance actual or simulated initiation signal. with the Surveillance Frequency Control Program SR 3.6.4.3.4     Verify each SGT filter cooling bypass     In accordance damper can be opened and the fan         with the started.                                  Surveillance Frequency Control Program CLINTON                          3.6-53                    Amendment No. 201
In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling bypass damper can be opened and the fan started.
In accordance with the Surveillance Frequency Control Program  


Control Room Ventilation System 3.7.3 3.7 PLANT SYSTEM 3.7.3   Control Room Ventilation System LCO 3.7.3       Two Control Room Ventilation subsystems shall be OPERABLE.
Control Room Ventilation System 3.7.3 CLINTON 3.7-4 Amendment No. 9 5 3.7 PLANT SYSTEM 3.7.3 Control Room Ventilation System LCO 3.7.3 Two Control Room Ventilation subsystems shall be OPERABLE.  
                  --------------------------NOTE---------------------------
--------------------------NOTE---------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY:   MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION           COMPLETION TIME A. One Control Room         A.1     Restore Control Room   7 days Ventilation                      Ventilation subsystem subsystem inoperable              to OPERABLE status.
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.
for reasons other than Condition C.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Control Room Ventilation subsystem inoperable for reasons other than Condition C.
B. Required Action and     ------------NOTE-------------
A.1 Restore Control Room Ventilation subsystem to OPERABLE status.
associated              LCO 3.0.4.a is not Completion Time of      applicable when entering Condition A not met    MODE 3.
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
in MODE 1, 2, or 3.    -----------------------------
------------NOTE-------------
B.1     Be in MODE 3.           12 hours C. One or more Control     C.1      Initiate action to      Immediately Room Ventilation                 implement mitigating subsystems inoperable           actions.
LCO 3.0.4.a is not applicable when entering MODE 3.
due to inoperable CRE   AND boundary in MODE 1, 2, or 3.               C.2     Verify mitigating       24 hours actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
B.1 Be in MODE 3.
AND C.3     Restore CRE boundary   90 days to OPERABLE status.
12 hours C. One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.
(continued)
C.1 Initiate action to implement mitigating actions.
CLINTON                              3.7-4                    Amendment No. 9 5
AND C.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND C.3 Restore CRE boundary to OPERABLE status.
Immediately 24 hours 90 days (continued)  


Control Room Ventilation System 3.7.3 ACTIONS   (continued)
Control Room Ventilation System 3.7.3 CLINTON 3.7-5 Amendment No.
CONDITION                 REQUIRED ACTION         COMPLETION TIME D. Required Action and   D.1      Be in MODE 3.          12 hours Associated Completion Time of Condition C not met in MODE 1, 2, AND or 3.
ACTIONS (continued)
D.2     Be in MODE 4.           36 hours E. Required Action and   ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and Associated Completion Time of Condition C not met in MODE 1, 2, or 3.
associated Completion  LCO 3.0.3 is not applicable.
D.1 Be in MODE 3.
Time of Condition A    -----------------------------
AND D.2 Be in MODE 4.
not met during movement of irradiated E.1     Place OPERABLE         Immediately fuel assemblies in the          Control Room primary or secondary            Ventilation subsystem containment, or during          in high radiation CORE ALTERATIONS.              mode.
12 hours 36 hours E. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
OR E.2.1   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
------------NOTE-------------
AND E.2.2   Suspend CORE           Immediately ALTERATIONS.
LCO 3.0.3 is not applicable.
F. Two Control Room       ------------NOTE-------------
E.1 Place OPERABLE Control Room Ventilation subsystem in high radiation mode.
Ventilation subsystems LCO 3.0.4.a is not inoperable in MODE 1,  applicable when entering 2, or 3 for reasons    MODE 3.
OR E.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
other than Condition  -----------------------------
AND E.2.2 Suspend CORE ALTERATIONS.
C.
Immediately Immediately Immediately F. Two Control Room Ventilation subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition C.
F.1     Be in MODE 3.           12 hours (continued)
------------NOTE-------------
CLINTON                            3.7-5                  Amendment No.
LCO 3.0.4.a is not applicable when entering MODE 3.
F.1 Be in MODE 3.
12 hours (continued)


Control Room Ventilation System 3.7.3 ACTIONS (continued)
Control Room Ventilation System 3.7.3 CLINTON 3.7-6 Amendment No.
CONDITION                   REQUIRED ACTION           COMPLETION TIME G. Two Control Room         G.1      Suspend movement of    Immediately Ventilation subsystems           irradiated fuel inoperable during                 assemblies in the movement of irradiated           primary and secondary fuel assemblies in the           containment.
ACTIONS (continued)
primary or secondary containment, or during   AND CORE ALTERATIONS.
CONDITION REQUIRED ACTION COMPLETION TIME G. Two Control Room Ventilation subsystems inoperable during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
G.2      Suspend CORE            Immediately OR                                   ALTERATIONS.
OR One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
G.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.7.3.1   Operate each Control Room Ventilation           In accordance subsystem with flow through the makeup         with the filter for 15 continuous minutes with the     Surveillance heaters operating.                             Frequency Control Program SR 3.7.3.2   Operate each Control Room Ventilation           In accordance subsystem with flow through the                with the recirculation filter for 15 minutes.         Surveillance Frequency Control Program (continued)
AND G.2 Suspend CORE ALTERATIONS.
CLINTON                              3.7-6                  Amendment No.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each Control Room Ventilation subsystem with flow through the makeup filter for 15 continuous minutes with the heaters operating.
In accordance with the Surveillance Frequency Control Program SR 3.7.3.2 Operate each Control Room Ventilation subsystem with flow through the recirculation filter for 15 minutes.
In accordance with the Surveillance Frequency Control Program (continued)  


Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4       Two control room AC subsystems shall be OPERABLE.
Control Room AC System 3.7.4 CLINTON 3.7-8 Amendment No. 9 5 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.
APPLICABILITY:   MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.
APPLICABILITY:
ACTIONS CONDITION                 REQUIRED ACTION           COMPLETION TIME A. One control room AC     A.1     Restore control room   30 days subsystem inoperable.            AC subsystem to OPERABLE status.
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.
B. Two control room AC     B.1     Verify control room     Once per 4 hours subsystems inoperable.          area temperature 86 &#xba;F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC subsystem inoperable.
AND B.2     Restore one control     7 days room AC subsystem to OPERABLE status.
A.1 Restore control room AC subsystem to OPERABLE status.
C. Required Action and     -------------NOTE------------
30 days B. Two control room AC subsystems inoperable.
Associated Completion  LCO 3.0.4.a is not applicable Time of Condition A or  when entering MODE 3.
B.1 Verify control room area temperature 86 &#xba;F.
B not met in MODE 1,    -----------------------------
AND B.2 Restore one control room AC subsystem to OPERABLE status.
2, or 3.
Once per 4 hours 7 days C. Required Action and Associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.
C.1     Be in MODE 3.           12 hours (continued)
-------------NOTE------------
CLINTON                              3.7-8                    Amendment No. 9 5
LCO 3.0.4.a is not applicable when entering MODE 3.
C.1 Be in MODE 3.
12 hours (continued)  


Control Room AC System 3.7.4 ACTIONS (continued)
Control Room AC System 3.7.4 CLINTON 3.7-9 Amendment No. 95 ACTIONS (continued)
CONDITION                 REQUIRED ACTION           COMPLETION TIME D. Required Action and   ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
associated Completion  LCO 3.0.3 is not applicable.
------------NOTE-------------
Time of Condition A    -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of irradiated D.1     Place OPERABLE         Immediately fuel assemblies in the          control room AC primary or secondary            subsystem in containment, or during          operation.
D.1 Place OPERABLE control room AC subsystem in operation.
CORE ALTERATIONS.
OR D.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
OR D.2.1   Suspend movement of     Immediately irradiated fuel assemblies in the primary and secondary containment.
AND D.2.2 Suspend CORE ALTERATIONS.
AND D.2.2   Suspend CORE           Immediately ALTERATIONS.
Immediately Immediately Immediately (continued)
(continued)
CLINTON                            3.7-9                    Amendment No. 95


Control Room AC System 3.7.4 ACTIONS (continued)
Control Room AC System 3.7.4 CLINTON 3.7-10 Amendment No. 95 ACTIONS (continued)
CONDITION                   REQUIRED ACTION           COMPLETION TIME E. Required Action and     ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition B not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.
associated Completion    LCO 3.0.3 is not applicable.
------------NOTE-------------
Time of Condition B      -----------------------------
LCO 3.0.3 is not applicable.
not met during movement of irradiated  E.1     Suspend movement of     Immediately fuel assemblies in the            irradiated fuel primary or secondary              assemblies in the containment, or during            primary and secondary CORE ALTERATIONS.                containment.
E.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND E.2     Suspend CORE           Immediately ALTERATIONS.
AND E.2 Suspend CORE ALTERATIONS.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.7.4.1   Verify each control room AC subsystem has       In accordance the capability to remove the assumed heat       with the load.                                          Surveillance Frequency Control Program CLINTON                              3.7-10                    Amendment No. 95
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the capability to remove the assumed heat load.
In accordance with the Surveillance Frequency Control Program  


AC Sources Shutdown 3.8.2 3.8   ELECTRICAL POWER SYSTEMS 3.8.2   AC Sources Shutdown LCO   3.8.2       The following AC electrical power sources shall be OPERABLE:
AC Sources Shutdown 3.8.2 CLINTON 3.8-16 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
: a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";
: a.
: b. One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and
One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";
: c. One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
: b.
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and
ACTIONS
: c.
One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
ACTIONS  
---------------------------------------NOTE----------------------------------
---------------------------------------NOTE----------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
(continued)
(continued)  
CLINTON                              3.8-16                  Amendment No. XXX


AC Sources Shutdown 3.8.2 ACTIONS (continued)
AC Sources Shutdown 3.8.2 CLINTON 3.8-17 Amendment No. 95 ACTIONS (continued)
CONDITION             REQUIRED ACTION         COMPLETION TIME A. LCO Item a not met. ------------NOTE-------------
CONDITION REQUIRED ACTION COMPLETION TIME A. LCO Item a not met.  
------------NOTE-------------
Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.
Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.
A.1     Declare affected       Immediately required feature(s) with no offsite power available from a required circuit inoperable.
A.1 Declare affected required feature(s) with no offsite power available from a required circuit inoperable.
OR A.2.1   Suspend CORE           Immediately ALTERATIONS.
OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2   Suspend movement of   Immediately irradiated fuel assemblies in the primary and secondary containment.
AND A.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
AND A.2.3   Initiate action to     Immediately restore required offsite power circuit to OPERABLE status.
AND A.2.3 Initiate action to restore required offsite power circuit to OPERABLE status.
(continued)
Immediately Immediately Immediately Immediately (continued)  
CLINTON                            3.8-17                Amendment No. 95


AC Sources Shutdown 3.8.2 ACTIONS (continued)
AC Sources Shutdown 3.8.2 CLINTON 3.8-18 Amendment No. 95 ACTIONS (continued)
CONDITION             REQUIRED ACTION         COMPLETION TIME B. LCO Item b not met. B.1     Suspend CORE           Immediately ALTERATIONS.
CONDITION REQUIRED ACTION COMPLETION TIME B. LCO Item b not met.
AND B.2     Suspend movement of   Immediately irradiated fuel assemblies in primary and secondary containment.
B.1 Suspend CORE ALTERATIONS.
AND B.3 Initiate action to         Immediately restore required DG to OPERABLE status.
AND B.2 Suspend movement of irradiated fuel assemblies in primary and secondary containment.
C. LCO Item c not met. C.1     Declare High Pressure 72 hours Core Spray System inoperable.
AND B.3 Initiate action to restore required DG to OPERABLE status.
CLINTON                        3.8-18                  Amendment No. 95
Immediately Immediately Immediately C. LCO Item c not met.
C.1 Declare High Pressure Core Spray System inoperable.
72 hours


DC Sources Shutdown 3.8.5 3.8   ELECTRICAL POWER SYSTEMS 3.8.5   DC Sources Shutdown LCO   3.8.5       The following shall be OPERABLE:
DC Sources Shutdown 3.8.5 CLINTON 3.8-27 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 The following shall be OPERABLE:
: a. One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -
: a.
One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -
Shutdown";
Shutdown";
: b. One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and
: b.
: c. The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
: c.
ACTIONS
The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
ACTIONS  
-------------------------------------NOTE-------------------------------------
-------------------------------------NOTE-------------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. One battery charger     A.1     Restore battery         2 hours on one division                    terminal voltage to inoperable.                      greater than or equal to the minimum established float voltage.
CONDITION REQUIRED ACTION COMPLETION TIME A.
AND A.2     Verify battery float   Once per 12 current < 2 amps.       hours AND A.3     Restore battery         7 days charger to OPERABLE status.
One battery charger on one division inoperable.
(continued)
A.1 Restore battery terminal voltage to greater than or equal to the minimum established float voltage.
CLINTON                              3.8-27                    Amendment No. XXX
AND A.2 Verify battery float current < 2 amps.
AND A.3 Restore battery charger to OPERABLE status.
2 hours Once per 12 hours 7 days (continued)  


DC Sources Shutdown 3.8.5 ACTIONS (continued)
DC Sources Shutdown 3.8.5 CLINTON 3.8-28 Amendment No. 142 ACTIONS (continued)
CONDITION                 REQUIRED ACTION         COMPLETION TIME B. One or more required   B.1      Declare affected      Immediately DC electrical power             required feature(s) subsystems inoperable           inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required DC electrical power subsystems inoperable for reasons other than Condition A.
for reasons other than Condition A.           OR OR B.2.1    Suspend CORE          Immediately Required Action and             ALTERATIONS.
OR Required Action and associated Completion Time of Condition A not met.
associated Completion Time of Condition A       AND not met.
B.1 Declare affected required feature(s) inoperable.
B.2.2   Suspend movement of   Immediately irradiated fuel assemblies in the primary and secondary containment.
OR B.2.1 Suspend CORE ALTERATIONS.
AND B.2.3   Initiate action to     Immediately restore required DC electrical power subsystems to OPERABLE status.
AND Immediately Immediately B.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
CLINTON                            3.8-28                  Amendment No. 142
AND Immediately B.2.3 Initiate action to restore required DC electrical power subsystems to OPERABLE status.
Immediately


Inverters-Shutdown 3.8.8 3.8   ELECTRICAL POWER SYSTEMS 3.8.8   Inverters Shutdown LCO   3.8.8       The following Divisional inverters shall be OPERABLE:
Inverters-Shutdown 3.8.8 CLINTON 3.8-36 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters Shutdown LCO 3.8.8 The following Divisional inverters shall be OPERABLE:
: a. One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and
: a.
: b. The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and
APPLICABILITY:   MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.
: b.
CLINTON                              3.8-36                  Amendment No. XXX
The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.
APPLICABILITY:
MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.  


Inverters Shutdown 3.8.8 ACTIONS
Inverters Shutdown 3.8.8 CLINTON 3.8-37 Amendment No. 95 ACTIONS  
------------------------------------------NOTE-------------------------------
------------------------------------------NOTE-------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
CONDITION                 REQUIRED ACTION           COMPLETION TIME A. One or more required   A.1     Declare affected       Immediately divisional inverters            required feature(s) inoperable.                      inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required divisional inverters inoperable.
OR A.2.1   Suspend CORE           Immediately ALTERATIONS.
A.1 Declare affected required feature(s) inoperable.
AND A.2.2   Suspend handling of     Immediately irradiated fuel assemblies in the primary and secondary containment.
OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.3   Initiate action to     Immediately restore required divisional inverters to OPERABLE status.
AND Immediately Immediately A.2.2 Suspend handling of irradiated fuel assemblies in the primary and secondary containment.
CLINTON                            3.8-37                      Amendment No. 95
AND Immediately A.2.3 Initiate action to restore required divisional inverters to OPERABLE status.
Immediately


Distribution Systems Shutdown 3.8.10 ACTIONS (continued)
Distribution Systems Shutdown 3.8.10 CLINTON 3.8-43 Amendment No. 192 ACTIONS (continued)
CONDITION                   REQUIRED ACTION           COMPLETION TIME A. (continued)             A.2.3   Initiate actions to     Immediately restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
AND A.2.4   Declare associated     Immediately required shutdown cooling subsystem(s) inoperable and not in operation.
A.2.3 Initiate actions to restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY SR 3.8.10.1   Verify correct breaker alignments and           In accordance voltage to required AC, DC, and                 with the uninterruptible AC bus electrical power         Surveillance distribution subsystems.                       Frequency Control Program CLINTON                              3.8-43                  Amendment No. 192
AND A.2.4 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and uninterruptible AC bus electrical power distribution subsystems.
In accordance with the Surveillance Frequency Control Program  


Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 4 TECHNICAL SPECIFICATIONS BASES PAGES AFFECTED BY THE ADDITIONAL VARIATION (MARK-UP)
Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 4 TECHNICAL SPECIFICATIONS BASES PAGES AFFECTED BY THE ADDITIONAL VARIATION (MARK-UP)
B 3.3-122c B 3.3-122d B 3.3-122e B 3.3-122f B 3.3-122g B 3.3-122h B 3.3-122i B 3.5-26
B 3.3-122c B 3.3-122d B 3.3-122e B 3.3-122f B 3.3-122g B 3.3-122h B 3.3-122i B 3.5-26  


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES APPLICABLE       Low Pressure Core Spray and Low Pressure Coolant Injection SAFETY           Systems ANALYSES, LCO, and APPLICABILITY 1.a, 2.a. Reactor Vessel Pressure - Low (Injection (continued)   Permissive)
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122c Revision No. 0 BASES APPLICABLE Low Pressure Core Spray and Low Pressure Coolant Injection SAFETY Systems ANALYSES, LCO, and APPLICABILITY 1.a, 2.a. Reactor Vessel Pressure - Low (Injection (continued)
Permissive)
Low reactor vessel pressure signals are used as permissives for the low pressure ECCS subsystems. This ensures that, prior to opening the injection valves of the low pressure ECCS subsystems, the reactor pressure has fallen to a value below these subsystems' maximum design pressure. While it is assured during Modes 4 and 5 that the reactor vessel pressure will be below the ECCS maximum design pressure, the Reactor vessel Pressure - Low signals are assumed to be operable and capable of permitting initiation of the ECCS.
Low reactor vessel pressure signals are used as permissives for the low pressure ECCS subsystems. This ensures that, prior to opening the injection valves of the low pressure ECCS subsystems, the reactor pressure has fallen to a value below these subsystems' maximum design pressure. While it is assured during Modes 4 and 5 that the reactor vessel pressure will be below the ECCS maximum design pressure, the Reactor vessel Pressure - Low signals are assumed to be operable and capable of permitting initiation of the ECCS.
The Reactor Vessel Pressure - Low signals are initiated from four pressure transmitters that sense the reactor dome pressure. The four pressure transmitters each drive ATMs (with a total of eight trip channels).
The Reactor Vessel Pressure - Low signals are initiated from four pressure transmitters that sense the reactor dome pressure. The four pressure transmitters each drive ATMs (with a total of eight trip channels).
Line 1,728: Line 2,243:
One flow transmitter per ECCS pump is used to detect the associated subsystems' flow rates. The logic is arranged such that each transmitter causes its associated minimum flow valve to open. The logic will close the minimum flow valve once the closure setpoint is exceeded. The LPCI minimum flow valves are time delayed such that the valves will not open for 8 seconds after the ATMs detect low flow.
One flow transmitter per ECCS pump is used to detect the associated subsystems' flow rates. The logic is arranged such that each transmitter causes its associated minimum flow valve to open. The logic will close the minimum flow valve once the closure setpoint is exceeded. The LPCI minimum flow valves are time delayed such that the valves will not open for 8 seconds after the ATMs detect low flow.
The time delay is provided to limit reactor vessel inventory loss during the startup of the Residual Heat Removal (RHR) shutdown cooling mode (for RHR A and RHR B).
The time delay is provided to limit reactor vessel inventory loss during the startup of the Residual Heat Removal (RHR) shutdown cooling mode (for RHR A and RHR B).
(continued)
(continued)  
CLINTON                        B 3.3-122c                        Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES APPLICABLE       The Pump Discharge Flow - Low Allowable Values are high SAFETY           enough to ensure that the pump flow rate is sufficient to ANALYSES, LCO,   protect the pump, yet low enough to ensure that the closure and APPLICABILITY of the minimum flow valve is initiated to allow full flow (continued)   into the core.
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122d Revision No. 0 BASES APPLICABLE The Pump Discharge Flow - Low Allowable Values are high SAFETY enough to ensure that the pump flow rate is sufficient to ANALYSES, LCO, protect the pump, yet low enough to ensure that the closure and APPLICABILITY of the minimum flow valve is initiated to allow full flow (continued) into the core.
One channel of the Pump Discharge Flow - Low Function is required to be OPERABLE in MODES 4 and 5 when the associated LPCS or LPCI pump is required to be OPERABLE by LCO 3.5.2 to ensure the pumps are capable of injecting into the Reactor Pressure Vessel when manually initiated.
One channel of the Pump Discharge Flow - Low Function is required to be OPERABLE in MODES 4 and 5 when the associated LPCS or LPCI pump is required to be OPERABLE by LCO 3.5.2 to ensure the pumps are capable of injecting into the Reactor Pressure Vessel when manually initiated.
High Pressure Core Spray System 3.a. Reactor Core Isolation Cooling (RCIC) Storage Tank Level - Low Low level in the RCIC Storage Tank indicates the unavailability of an adequate supply of makeup water from this normal source. Normally the suction valves between HPCS and the RCIC Storage Tank are open and water for HPCS injection would be taken from the RCIC Storage Tank.
High Pressure Core Spray System 3.a. Reactor Core Isolation Cooling (RCIC) Storage Tank Level - Low Low level in the RCIC Storage Tank indicates the unavailability of an adequate supply of makeup water from this normal source. Normally the suction valves between HPCS and the RCIC Storage Tank are open and water for HPCS injection would be taken from the RCIC Storage Tank.
Line 1,738: Line 2,252:
The RCIC Storage Tank Level - Low Function Allowable Value is high enough to ensure adequate pump suction head while water is being taken from the RCIC Storage Tank.
The RCIC Storage Tank Level - Low Function Allowable Value is high enough to ensure adequate pump suction head while water is being taken from the RCIC Storage Tank.
Two channels of the RCIC Storage Tank Level - Low Function are only required to be OPERABLE when HPCS is required to be OPERABLE to fulfill the requirements of LCO 3.5.2, HPCS is aligned to the RCIC Storage Tank, and the RCIC Storage Tank water level is not within the limits of SR 3.5.2.3.
Two channels of the RCIC Storage Tank Level - Low Function are only required to be OPERABLE when HPCS is required to be OPERABLE to fulfill the requirements of LCO 3.5.2, HPCS is aligned to the RCIC Storage Tank, and the RCIC Storage Tank water level is not within the limits of SR 3.5.2.3.
(continued)
(continued)  
CLINTON                        B 3.3-122d                      Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES APPLICABLE       3.b, 3.c. HPCS Pump Discharge Pressure - High (Bypass) and SAFETY           HPCS System Flow Rate - Low (Bypass)
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122e Revision No. 0 BASES APPLICABLE 3.b, 3.c. HPCS Pump Discharge Pressure - High (Bypass) and SAFETY HPCS System Flow Rate - Low (Bypass)
ANALYSES, LCO, and APPLICABILITY The minimum flow instruments are provided to protect the (continued)   HPCS pump from overheating when the pump is operating and the associated injection valve is not fully open. The minimum flow line valve is opened when low flow and high pump discharge pressure are sensed, and the valve is automatically closed when the flow rate is adequate to protect the pump or the discharge pressure is low (indicating the HPCS pump is not operating).
ANALYSES, LCO, and APPLICABILITY The minimum flow instruments are provided to protect the (continued)
HPCS pump from overheating when the pump is operating and the associated injection valve is not fully open. The minimum flow line valve is opened when low flow and high pump discharge pressure are sensed, and the valve is automatically closed when the flow rate is adequate to protect the pump or the discharge pressure is low (indicating the HPCS pump is not operating).
One flow transmitter is used to detect the HPCS System's flow rate. The logic is arranged such that the transmitter causes the minimum flow valve to open, provided the HPCS pump discharge pressure, sensed by another transmitter, is high enough (indicating the pump is operating). The logic will close the minimum flow valve once the closure setpoint is exceeded. (The valve will also close upon HPCS pump discharge pressure decreasing below the setpoint.)
One flow transmitter is used to detect the HPCS System's flow rate. The logic is arranged such that the transmitter causes the minimum flow valve to open, provided the HPCS pump discharge pressure, sensed by another transmitter, is high enough (indicating the pump is operating). The logic will close the minimum flow valve once the closure setpoint is exceeded. (The valve will also close upon HPCS pump discharge pressure decreasing below the setpoint.)
The HPCS System Flow Rate - Low and HPCS Pump Discharge Pressure - High Allowable Value is high enough to ensure that pump flow rate is sufficient to protect the pump, yet low enough to ensure that the closure of the minimum flow valve is initiated to allow full flow into the core.
The HPCS System Flow Rate - Low and HPCS Pump Discharge Pressure - High Allowable Value is high enough to ensure that pump flow rate is sufficient to protect the pump, yet low enough to ensure that the closure of the minimum flow valve is initiated to allow full flow into the core.
The HPCS Pump Discharge Pressure - High Allowable Value is set high enough to ensure that the valve will not be open when the pump is not operating.
The HPCS Pump Discharge Pressure - High Allowable Value is set high enough to ensure that the valve will not be open when the pump is not operating.
One channel of each Function is required to be OPERABLE when HPCS is required to be OPERABLE by LCO 3.5.2 in MODES 4 and 5.
One channel of each Function is required to be OPERABLE when HPCS is required to be OPERABLE by LCO 3.5.2 in MODES 4 and 5.
(continued)
(continued)  
CLINTON                        B 3.3-122e                      Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES APPLICABLE       RHR System Isolation SAFETY ANALYSES, LCO,   4.a - Reactor Vessel Water Level - Low. Level 3 and APPLICABILITY (continued)   The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low, Level 3 Function is only required to be OPERABLE when automatic isolation of the associated RHR penetration flow path is credited in calculating DRAIN TIME.
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122f Revision No. 0 BASES APPLICABLE RHR System Isolation SAFETY ANALYSES, LCO, 4.a - Reactor Vessel Water Level - Low. Level 3 and APPLICABILITY (continued)
The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low, Level 3 Function is only required to be OPERABLE when automatic isolation of the associated RHR penetration flow path is credited in calculating DRAIN TIME.
Reactor Vessel Water Level - Low, Level 3 signals are initiated from four level transmitters (two per trip system) that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.
Reactor Vessel Water Level - Low, Level 3 signals are initiated from four level transmitters (two per trip system) that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.
While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 3 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.
While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 3 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.
The Reactor Vessel Water Level - Low, Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low, Level 3 Allowable Value (LCO 3.3.1.1),
The Reactor Vessel Water Level - Low, Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low, Level 3 Allowable Value (LCO 3.3.1.1),
since the capability to cool the fuel may be threatened.
since the capability to cool the fuel may be threatened.
(continued)
(continued)  
CLINTON                        B 3.3-122f                      Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES APPLICABLE       Reactor Water Cleanup (RWCU) System Isolation SAFETY ANALYSES, LCO,   5.a - Reactor Vessel Water level - Low Low, Level 2 and APPLICABILITY (continued)   The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low Low, Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration flow paths associated with the RWCU System.
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122g Revision No. 0 BASES APPLICABLE Reactor Water Cleanup (RWCU) System Isolation SAFETY ANALYSES, LCO, 5.a - Reactor Vessel Water level - Low Low, Level 2 and APPLICABILITY (continued)
The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low Low, Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration flow paths associated with the RWCU System.
Reactor Vessel Water Level - Low Low, Level 2 is initiated from two channels per trip system that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 2 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.
Reactor Vessel Water Level - Low Low, Level 2 is initiated from two channels per trip system that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 2 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.
The Reactor Vessel Water Level - Low Low, Level 2 Allowable Value was chosen to be the same as the ECCS Reactor Vessel Water Level - Low Low, Level 2 Allowable Value (LCO 3.3.5.1), since the capability to cool the fuel may be threatened.
The Reactor Vessel Water Level - Low Low, Level 2 Allowable Value was chosen to be the same as the ECCS Reactor Vessel Water Level - Low Low, Level 2 Allowable Value (LCO 3.3.5.1), since the capability to cool the fuel may be threatened.
The Reactor Vessel Water Level - Low Low, Level 2 Function is only required to be OPERABLE when automatic isolation of the associated penetration flow path is credited in calculating DRAIN TIME.
The Reactor Vessel Water Level - Low Low, Level 2 Function is only required to be OPERABLE when automatic isolation of the associated penetration flow path is credited in calculating DRAIN TIME.
ACTIONS           A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels.
ACTIONS A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels.
Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits (continued)
Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits (continued)  
CLINTON                        B 3.3-122g                      Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES ACTIONS       will not result in separate entry into the Condition.
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122h Revision No. 0 BASES ACTIONS will not result in separate entry into the Condition.
(continued) Section 1.3 also specifies that Required Actions continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory measures for separate inoperable Condition entry for each inoperable RPV Water Inventory Control instrumentation channel.
(continued)
Section 1.3 also specifies that Required Actions continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory measures for separate inoperable Condition entry for each inoperable RPV Water Inventory Control instrumentation channel.
A.1 Required Action A.1 directs entry into the appropriate Condition referenced in Table 3.3.5.2-1. The applicable Condition referenced in the Table is Function dependent.
A.1 Required Action A.1 directs entry into the appropriate Condition referenced in Table 3.3.5.2-1. The applicable Condition referenced in the Table is Function dependent.
Each time a channel is discovered inoperable, Condition A is entered for that channel and provides for transfer to the appropriate subsequent Condition.
Each time a channel is discovered inoperable, Condition A is entered for that channel and provides for transfer to the appropriate subsequent Condition.
Line 1,773: Line 2,287:
C.1 Low reactor vessel pressure signals are used as permissives for the low pressure ECCS injection/spray subsystem manual initiation functions. If this permissive is inoperable, manual initiation of ECCS is prohibited. Therefore, the permissive must be placed in the trip condition within 1 hour. With the permissive in the trip condition, manual initiation may be performed. Prior to placing the permissive in the tripped condition, the operator can take manual control of the pump and the injection valve to inject water into the RPV.
C.1 Low reactor vessel pressure signals are used as permissives for the low pressure ECCS injection/spray subsystem manual initiation functions. If this permissive is inoperable, manual initiation of ECCS is prohibited. Therefore, the permissive must be placed in the trip condition within 1 hour. With the permissive in the trip condition, manual initiation may be performed. Prior to placing the permissive in the tripped condition, the operator can take manual control of the pump and the injection valve to inject water into the RPV.
The Completion Time of 1 hour is intended to allow the operator time to evaluate any discovered inoperabilities and to place the channel in trip.
The Completion Time of 1 hour is intended to allow the operator time to evaluate any discovered inoperabilities and to place the channel in trip.
(continued)
(continued)  
CLINTON                    B 3.3-122h                      Revision No. 0


RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES ACTIONS       D.1 and D.2 (continued)
RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122i Revision No. 0 BASES ACTIONS D.1 and D.2 (continued)
Required Actions D.1 and D.2 are intended to ensure that appropriate actions are taken if multiple, inoperable channels within the same Function result in a loss of automatic suction swap for the HPCS system from the RCIC storage tank to the suppression pool. The HPCS system must be declared inoperable within 1 hour or the HPCS pump suction must be aligned to the suppression pool, since, if aligned, the function is already performed.
Required Actions D.1 and D.2 are intended to ensure that appropriate actions are taken if multiple, inoperable channels within the same Function result in a loss of automatic suction swap for the HPCS system from the RCIC storage tank to the suppression pool. The HPCS system must be declared inoperable within 1 hour or the HPCS pump suction must be aligned to the suppression pool, since, if aligned, the function is already performed.
The 1 hour Completion Time is acceptable because it minimizes the risk of HPCS being needed without an adequate water source while allowing time for restoration or alignment of HPCS pump suction to the suppression pool.
The 1 hour Completion Time is acceptable because it minimizes the risk of HPCS being needed without an adequate water source while allowing time for restoration or alignment of HPCS pump suction to the suppression pool.
Line 1,783: Line 2,296:
F.1 With the Required Action and associated Completion Time of Conditions C, D, E, or F not met, the associated ECCS injection/spray subsystem may be incapable of performing the intended function, and must be declared inoperable immediately.
F.1 With the Required Action and associated Completion Time of Conditions C, D, E, or F not met, the associated ECCS injection/spray subsystem may be incapable of performing the intended function, and must be declared inoperable immediately.
(continued)
(continued)
CLINTON                    B 3.3-122i                        Revision No. 0


ECCS-ShutdownRPV Water Inventory Control B 3.5.2 BASES SURVEILLANCE   SR 3.5.2.8SR 3.5.2.4 (continued)
ECCS-ShutdownRPV Water Inventory Control B 3.5.2 CLINTON B 3.5-26 Revision No. 17-1 BASES SURVEILLANCE SR 3.5.2.8SR 3.5.2.4 (continued)
REQUIREMENTS (continued) in the correct position. The required ECCS subsystem shall be capable of being manually operated. This Surveillance verifies that the required LCPI subsystem, LPCS System, or HPCS System (including the associated pump and valve(s)) can be manually operated to provide additional RPV Water Inventory, if needed, without delay.
REQUIREMENTS (continued) in the correct position. The required ECCS subsystem shall be capable of being manually operated. This Surveillance verifies that the required LCPI subsystem, LPCS System, or HPCS System (including the associated pump and valve(s)) can be manually operated to provide additional RPV Water Inventory, if needed, without delay.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
This SR is modified by a Note that excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.
This SR is modified by a Note that excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.
REFERENCES     1. Information Notice 84-81 "Inadvertent Reduction in Primary Coolant Inventory in Boiling Water Reactors During Shutdown and Startup," November 1984.
REFERENCES
: 2. Information Notice 86-74, "Reduction of Reactor Coolant Inventory Because of Misalignment of RHR Valves," August 1986.
: 1.
: 3. Generic Letter 92-04, "Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f)," August 1992.
Information Notice 84-81 "Inadvertent Reduction in Primary Coolant Inventory in Boiling Water Reactors During Shutdown and Startup," November 1984.
: 4. NRC Bulletin 93-03, "Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs,"
: 2.
Information Notice 86-74, "Reduction of Reactor Coolant Inventory Because of Misalignment of RHR Valves," August 1986.
: 3.
Generic Letter 92-04, "Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f)," August 1992.
: 4.
NRC Bulletin 93-03, "Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs,"
May 1993.
May 1993.
: 5. Information Notice 94-52, "Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone 1,"
: 5.
Information Notice 94-52, "Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone 1,"
July 1994.
July 1994.
: 6. General Electric Service Information Letter No. 388, "RHR Valve Misalignment During Shutdown Cooling Operation for BWR 3/4/5/6," February 1983.
: 6.
CLINTON                        B 3.5-26                  Revision No. 17-1}}
General Electric Service Information Letter No. 388, "RHR Valve Misalignment During Shutdown Cooling Operation for BWR 3/4/5/6," February 1983.}}

Latest revision as of 16:41, 7 January 2025

Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
ML17319A297
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/15/2017
From: Simpson P
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CAC MF9666, RS-17-145
Download: ML17319A297 (161)
v • d • e


Text

4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-17-145 10 CFR 50.90 November 15, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control"

References:

(1)

Letter from P. R. Simpson (Exelon Generation Company, LLC (EGC)) to NRC, "Application to Revise Technical Specifications to Adopt TSTF-542,

'Reactor Pressure Vessel Water Inventory Control,'" dated April 27, 2017 (2)

Email from J. Rankin (NRC) to M. A. Mathews (EGC), "Clinton Power Station - Request for Additional Information Regarding License Amendment Request Related to Reactor Pressure Vessel Water Inventory Control (CAC No. MF9666)," dated October 3, 2017 In Reference 1, Exelon Generation Company, LLC (EGC) submitted a request for an amendment to the Technical Specifications (TS) for Clinton Power Station (CPS), Unit 1.

In Reference 2, the NRC determined that additional information was required to complete its evaluation of the Reference 1 request. The requested information, along with one additional variation from TSTF-542 related to the manual operation of a required emergency core cooling subsystem is provided in the attachments to this letter.

Additionally, on May 26, 2017, the NRC issued Operating License Amendment No. 212 for CPS, Unit 1. This amendment allows for the adoption of TSTF-545, "TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing." Attachment 2 to this letter provides revised markups of the CPS, Unit 1 TS to address issues identified in Reference 2, the adoption of TSTF-545, and the additional variation discussed above. These markups supersede those provided in Reference 1, Attachment 2 in their entirety. Attachment 3 provides the accompanying revised TS pages associated with the modifications shown in Attachment 2 as discussed above. Likewise, these pages supersede those provided in Reference 1, Attachment 3. Attachment 4 provides a markup of the TS Bases pages affected by the additional variation discussed above for information only.

November 15, 2017 U.S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC ln Reference 1.

The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

EGC is notifying the State of Illinois of this supplement to a previous application for a change to the TS by sending a copy of this letter and its attachment to the designated State Official in accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b).

Based on the NRC's review timeline associated with the Reference 1 request and recent discussions with the Office of Nuclear Reactor Regulation Project Manager for CPS, Unit 1, Jennivine Rankin, EGG proposes a revision to the implementation period for the Reference 1 request. EGC proposes that once the Reference 1 request is approved, the amendment shall be implemented for CPS, Unit 1 prior to entering Mode 4 during the next refueling outage, C1R18, currently planned for April 2018.

There are no regulatory commitments contained within this letter.

Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15th day of November 2017.

RfmR Patrick R. Simpson Manager-Licensing Exelon Generation Company, LLC Attachments:

1.

Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1

2.

Proposed Technical Specifications Changes (Mark-Up)

3.

Revised Technical Specifications Pages

4.

Technical Specifications Bases Pages Affected by the Additional Variation (Mark-Up}

cc:

NRG Regional Administrator, Region Ill NRC Senior Resident Inspector-Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety

Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 1 -

Supplemental Information Related to Request to Adopt TSTF-542, "Reactor Pressure Vessel (RPV) Water Inventory Control," for Clinton Power Station, Unit 1

SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 1 of 4 REQUEST FOR ADDITIONAL INFORMATION EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT 1 LICENSE AMENDMENT REQUEST RELATED TO REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL DOCKET NO. 50-461 By application dated May 1, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17121A517), Exelon Generation Company, LLC (the licensee),

requested a change to the technical specifications (TSs) for Clinton Power Station, Unit 1 (CPS). The proposed change adopts technical specifications task force (TSTF) traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2 (ADAMS Accession No. ML16074A448). Specifically, the proposed changes would replace the existing requirements in the TSs related to operation with a potential for draining the reactor vessels (OPDRVs) with revised TSs providing an alternative for reactor pressure vessel water inventory control (RPV WIC). These alternative requirements would protect Safety Limit 2.1.1.3, which requires RPV water level to be greater than the top of active fuel.

TSTF-542, Revision 2, was approved by the U.S. Nuclear Regulatory Commission (NRC) on December 20, 2016 (ADAMS Accession No. ML16343B008).

Based on its review of the amendment request, the NRC staff has determined that additional information is required to complete the review.

RAI 1

The staff has identified an apparent discrepancy in Attachment 2, page 3.5-11 of the license amendment request (LAR). Specifically, the current TSs (i.e., current TS surveillance requirements 3.5.2.5 and 3.5.2.6) contain text not shown in the proposed markup as being deleted.

For clarity, please correct the proposed TS markup, as appropriate Exelon Generation Company, LLC (EGC) Response The markups for SR 3.5.2.5 and SR 3.5.2.6 are incorporated in the revised TS markups included in Attachment 2 on Page 3.5-10.

SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 2 of 4

RAI 2

TSTF-542, Revision 2 changes the title of TS 3.5.2 from "ECCS - Shutdown" to "RPV Water Inventory Control." Current TS 3.8.2, "AC Sources - Shutdown," TS 3.8.5, "DC Sources -

Shutdown," and TS 3.8.8, "Inverters - Shutdown," reference TS 3.5.2, "ECCS-Shutdown."

There was not any revised TS pages submitted in the LAR to reflect the changes to these sections.

Please provide revised and markup TS pages for these sections, as appropriate.

EGC Response The requested changes are incorporated in the revised markups included in Attachment 2 on Pages 3.8-16, 3.8-27, and 3.8-36.

RAl 3

, pages 3.3-54 through 3.3-59 of the LAR provides a markup of Table 3.3.6.1-1, "Primary Containment and Drywell Isolation Instrumentation." Due to the deletion of Footnote (c), which states, "During operations with a potential for draining the reactor vessel," the following instrumentation were affected.

Function 2 (Primary Containment and drywell isolation), Item a, "Reactor Vessel Water Level Low Low, Level 2" Function 2, Item g, "Containment Building Fuel Transfer Pool Ventilation Plenum Radiation High" Function 2, Item h, "Containment Building Exhaust Radiation High" Function 2, Item i, "Containment Building Continuous Containment Purge (CCP) Exhaust Radiation High" Function 2, Item j, "Reactor Vessel Water Level Low Low Low, Level 1" Function 2, Item l, "Manual Initiation" Function 4 (reactor water cleanup system isolation), Item f, "Reactor Vessel Level Low Low, Level 2" Function 4, Item h, "Manual Initiation" Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation" in TSTF-542, Revision 2 modifies Function 2.g, "Containment and Drywell Ventilation Exhaust Radiation High," in relation to the removal of Footnote (b) which states, "or operations with a potential for draining the reactor vessel."

Compared to the TSTF-542, Revision 2, CPS proposed to delete additional instrumentation (related to the Applicability during Modes 4 and 5 or OPDRVs) from its TSs. Please provide a technical variation to describe the deviations between the proposed CPS TSs and TSTF 542, Revision 2.

SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 3 of 4 EGC Response All of these instrument functions serve to isolate Primary Containment penetrations that bypass Secondary Containment; therefore, they function to isolate a portion of the Secondary Containment boundary for Clinton Power Station (CPS), Unit 1. Under the proposed Technical Specification (TS) 3.5.2 "Reactor Pressure Vessel Water Inventory Control," requirements, Secondary Containment must be isolated or capable of being isolated in less than the Drain Time when the Drain Time is less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, but automatic Secondary Containment isolation is not required. A draining event is a slow evolution when compared to a design basis loss of coolant accident that is assumed to occur at full power, and thus there is adequate time to take manual actions (i.e., hours versus minutes). The proposed TS 3.5.2, Action E, prohibits plant conditions that could result in Drain Times less than one hour. Therefore, there is sufficient time for the licensed operators to take manual action to stop the draining event, or to establish the Secondary Containment boundary and to isolate the Secondary Containment penetration flow paths before Secondary Containment isolation would be required.

Consequently, there is no need for automatic initiation of Secondary Containment isolation to respond to an unexpected draining event. The Required Actions of proposed TS 3.5.2 will require Secondary Containment isolation, or verification that it can be manually isolated, when the Drain Time is less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and no draining event has occurred. This provides a greater level of safety. Excluding these functions from Table 3.3.5.2-1 is addressed by the proposed Limiting Condition for Operation (LCO) 3.5.2, "RPV Water Inventory Control." Specifically, by LCO 3.5.2, Required Actions C.1 and D.2 which are: "Verify secondary containment boundary is capable of being established in less than the DRAIN TIME," and "Initiate action to establish secondary containment boundary," respectively. This approach is consistent with Section 3.4.1.3 of the Justification for TSTF-542, Revision 2.

Additional Proposed Variation for Instrumentation Functions:

EGC proposes to revise Table 3.3.5.2-1, "RPV Water Inventory Control Instrumentation," to reflect the CPS, Unit 1 design. Specifically, Function 1, "Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS) Subsystems," Function 1.d, "Manual Initiation,"

Function 2, "LPCI B and LPCI C Subsystems," Function 2.c, "Manual Initiation," and Function 3, High Pressure Core Spray (HPCS) System, Function 3.a, "Reactor Vessel Water Level - High, Level 8," and Function 3.e, "Manual initiation," that appear in the BWR/6 Technical Specifications in TSTF-542 are no longer included in the CPS Technical Specifications as proposed. This corrects an issue in TSTF-542 associated with the BWR/5 and BWR/6 emergency core cooling system (ECCS) instrumentation requirements.

The purpose of the manual initiation functions is to allow manual actuation of the ECCS subsystems required by TS 3.5.2 to mitigate a draining event. Licensed operators in the Main Control Room have the capability to manually start the LPCI, LPCS, and HPCS pumps and to manually align valves to add water inventory, if needed. This can be accomplished without the "Manual Initiation" functions, and the "Reactor Vessel Water Level-High, Level 8" function associated with HPCS. If the water level is above Level 8, and HPCS is the required ECCS subsystem, the Level 8 function can be intentionally defeated to allow the HPCS injection valve to be opened, if needed to control inventory. All actions can be performed from the Main

SUPPLEMENTAL INFORMATION RELATED TO REQUEST TO ADOPT TSTF-542, "REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL," FOR CLINTON POWER STATION, UNIT 1 Page 4 of 4 Control Room and can be accomplished well within the one-hour minimum drain time limit specified in TS 3.5.2, Condition E.

The Reactor Vessel Water Level High, Level 8 signal (i.e., TSTF-542, Table 3.3.5.2-1, Function 3.a) prevents overfilling of the reactor vessel into the main steam lines by closing the HPCS injection valves when the water level is above the Level 8 setpoint. Therefore, if HPCS is the required ECCS subsystem and the water level is above Level 8, using the "Manual Initiation" Function 3.e will not result in inventory injection into the reactor vessel until the water level drops below the Level 8 setpoint. If the Level 8 function is retained in Table 3.3.5.2-1, the function would need to be rendered inoperable in order to inject water when the water level is above the Level 8 setpoint.

Consequently, Table 3.3.5.2-1, Functions 1.d, 2.c, 3.a, and 3.e, and TS 3.3.5.2, Condition E and associated Required Actions E.1, and E.2 as described in TSTF-542 are not needed to actuate the LPCI, LPCS, and HPCS subsystem components to mitigate a draining event, and are not included in the proposed Table 3.3.5.2-1 for CPS. The remaining functions and Conditions have been renumbered accordingly.

To address the changes associated with the proposed additional variation discussed above, EGC also proposes that Surveillance Requirement (SR) SR 3.5.2.8 be modified to verify that the CPS, Unit 1 required ECCS injection/spray subsystem can be manually operated from the Main Control Room in accordance with the Surveillance Frequency Control Program as shown in Figure 1 below. This will ensure that the required ECCS injection/spray subsystem is Operable and can be manually aligned to provide RPV inventory makeup, if required to do so, without delay.

Figure 1: Proposed SR 3.5.2.8

Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES (MARK-UP)

TOC Page ii TOC Page iii TOC Page iv 1.0-1 1.0-2 1.0-3 1.0-4 1.0-5 3.3-32 3.3-33 3.3-35 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-45 3.3-46 3.3-47 3.3-48 3.3-49 3.3-50 3.3-51 3.3-52 3.3-53 3.3-54 3.3-55 3.3-56 3.3-57 3.3-58 3.3-59 3.3-60 3.3-64 3.3-77 3.5-1 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 3.6-3 3.6-7 3.6-9 3.6-14 3.6-43 3.6-44 3.6-47 3.6-49 3.6-51 3.6-52 3.6-53 3.7-4 3.7-5 3.7-6 3.7-8 3.7-9 3.7-10 3.8-16 3.8-17 3.8-18 3.8-27 3.8-28 3.8-36 3.8-37 3.8-43

TABLE OF CONTENTS CLINTON Revision No. 2-13 iii B 3.3 INSTRUMENTATION (continued)

B 3.3.3.2 Remote Shutdown System....................................B 3.3-60 B 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation...........................................B 3.3-65 B 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B 3.3-76 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......B 3.3-85 B 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory ControlReactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123122a B 3.3.5.23 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123 B 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.........................B 3.3-135 B 3.3.6.2 Secondary Containment Isolation Instrumentation...........B 3.3-174 B 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B 3.3-186 B 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....B 3.3-197 B 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............B 3.3-208 B 3.3.7.1 Control Room Ventilation (CRV) System Instrumentation.....B 3.3-215 B 3.3.8.1 Loss of Power (LOP) Instrumentation.......................B 3.3-222 B 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.....................................B 3.3-230 3.4 REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1 Recirculation Loops Operating.............................3.4-1 3.4.2 Flow Control Valves (FCVs)................................3.4-6 3.4.3 Jet Pumps.................................................3.4-8 3.4.4 Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5 RCS Operational LEAKAGE...................................3.4-12 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7 RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8 RCS Specific Activity.....................................3.4-20 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown......................................3.4-22 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.....................................3.4-25 3.4.11 RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12 Reactor Steam Dome Pressure...............................3.4-33 B 3.4 REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1 Recirculation Loops Operating.............................B 3.4-1 B 3.4.2 Flow Control Valves (FCVs)................................B 3.4-9 (continued)

TABLE OF CONTENTS CLINTON Revision No. 14-2 iv B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

B 3.4.3 Jet Pumps.................................................B 3.4-13 B 3.4.4 Safety/Relief Valves (S/RVs)..............................B 3.4-17 B 3.4.5 RCS Operational LEAKAGE...................................B 3.4-23 B 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................B 3.4-28 B 3.4.7 RCS Leakage Detection Instrumentation.....................B 3.4-33 B 3.4.8 RCS Specific Activity.....................................B 3.4-39 B 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown..................................B 3.4-43 B 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................B 3.4-48 B 3.4.11 RCS Pressure and Temperature (P/T) Limits.................B 3.4-53 B 3.4.12 Reactor Steam Dome Pressure...............................B 3.4-63 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM..............................3.5-1 3.5.1 ECCS - Operating...........................................3.5-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown.................3.5-6 3.5.3 RCIC System...............................................3.5-1011 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................B 3.5-1 B 3.5.1 ECCS - Operating...........................................B 3.5-1 B 3.5.2 ECCS - ShutdownRPV Water Inventory Control.................B 3.5-1517 B 3.5.3 RCIC System...............................................B 3.5-2127 3.6 CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1 Primary Containment.......................................3.6-1 3.6.1.2 Primary Containment Air Locks.............................3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4 Primary Containment Pressure..............................3.6-20 3.6.1.5 Primary Containment Air Temperature.......................3.6-21 3.6.1.6 Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7 Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8 Deleted...................................................3.6-26 3.6.1.9 Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1 Suppression Pool Average Temperature......................3.6-28 3.6.2.2 Suppression Pool Water Level..............................3.6-31 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4 Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1 Deleted.................................................3.6-36 3.6.3.2 Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)

Definitions 1.1 CLINTON 1.0-1 Amendment No. 105 1.0 USE AND APPLICATION 1.1 Definitions

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR)

LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

(continued)

Definitions 1.1 CLINTON 1.0-2 Amendment No. 105 1.1 Definitions (continued)

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a.

The water inventory above the TAF is divided by the limiting drain rate;

b.

The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,

seismic event, loss of normal power, single human error), for all (continued)

Definitions 1.1 CLINTON 1.0-3 Amendment No. 105 Definitions DRAIN TIME penetration flow paths below the TAF except:

(continued)

1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation devices without offsite power.
c. The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;
d. No additional draining events occur; and
e. Realistic cross-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

Definitions 1.1 CLINTON 1.0-4 Amendment No. 105 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE associated turbine stop valve or turbine TIME control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE
1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;
b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;
c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

(continued)

Definitions 1.1 CLINTON 1.0-5 Amendment No. 95 128 1.1 Definitions (continued)

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3473 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-32 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

B.1

NOTES---------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions B.2

NOTES---------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 3.a and 3.b.

Declare High Pressure Core Spray (HPCS)

System inoperable.

AND B.3 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-33 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

C.1

NOTES--------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 1.c, 1.d, 2.c, and 2.d.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions C.2 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-35 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

E.1

NOTES---------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 1.e, 1.f, and 2.e.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND E.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions 7 days (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-39 Amendment No. 169 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems

a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3, 4(a),5(a) 2(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec)

-148.1 inches

b. Drywell Pressure-High 1,2,3 2(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. LPCI Pump A Start-Time Delay Logic Card 1,2,3, 4(a),5(a) 1 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds

d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 454 psig and 494 psig 4(a),5(a) 4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(e)

SR 3.3.5.1.4(e)

SR 3.3.5.1.5 454 psig and 494 psig

e. LPCS Pump Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 750 gpm

f. LPCI Pump A Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm

g. Manual Initiation 1,2,3, 4(a),5(a) 1 C

SR 3.3.5.1.5 NA (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(ba) Also required to initiate the associated diesel generator.

(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-40 Amendment No. 169 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. LPCI B and LPCI C Subsystems
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3, 4(a),5(a) 2(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec)

-148.1 inches

b. Drywell Pressure-High 1,2,3 2(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. LPCI Pump B Start-Time Delay Logic Card 1,2,3, 4(a),5(a) 1 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds

d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 454 psig and 494 psig 4(a),5(a) 4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(e)

SR 3.3.5.1.4(e)

SR 3.3.5.1.5 454 psig and 494 psig

e. LPCI Pump B and LPCI Pump C Discharge Flow-Low (Bypass) 1,2,3, 4(a),5(a) 1 per pump E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm

f. Manual Initiation 1,2,3, 4(a),5(a) 1 C

SR 3.3.5.1.5 NA (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(ba) Also required to initiate the associated diesel generator.

(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-41 Amendment No. 169 Table 3.3.5.1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. High Pressure Core Spray (HPCS) System
a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3, 4(a),5(a) 4(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec)

-48.1 inches

b. Drywell Pressure - High 1,2,3 4(ba)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. Reactor Vessel Water Level-High, Level 8 1,2,3, 4(a),5(a) 2 C

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec) 54.6 inches

d. RCIC Storage Tank Level-Low 1,2,3, 4(c),5(c) 2 D

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 3.0 inches

e. Suppression Pool Water Level-High 1,2,3 2

D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 11 inches

f. HPCS Pump Discharge Pressure-High (Bypass) 1,2,3, 4(a),5(a) 1 E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 120 psig

g. HPCS System Flow Rate-Low (Bypass) 1,2,3, 4(a),5(a) 1 E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 500 gpm

h. Manual Initiation 1,2,3, 4(a),5(a) 1 C

SR 3.3.5.1.5 NA (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(ba) Also required to initiate the associated diesel generator.

(c) When HPCS is OPERABLE for compliance with LCO 3.5.2, "ECCS-Shutdown," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.2.

(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-42 Amendment No. 169 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(db),3(db) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec)

-148.1 inches

b. Drywell Pressure-High 1,2(db),3(db) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. ADS Initiation Timer 1,2(db),3(db) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds

d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(db),3(db) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches

e. LPCS Pump Discharge Pressure-High 1,2(db),3(db) 2 G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 125 psig and

< 176.3 psig

f. LPCI Pump A Discharge Pressure-High 1,2(db),3(db) 2 G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 115 psig and

< 135 psig

g. ADS Drywell Pressure Bypass Timer 1,2(db),3(db) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes

h. Manual Initiation 1,2(db),3(db) 2 G

SR 3.3.5.1.5 NA (continued)

(d) (b) With reactor steam dome pressure > 150 psig.

(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-43 Amendment No. 169 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. ADS Trip System 2 (Logic B and F)
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(db),3(db) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.5 SR 3.3.5.1.6(ec)

-148.1 inches

b. Drywell Pressure-High 1,2(db),3(db) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. ADS Initiation Timer 1,2(db),3(db) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds

d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(db),3(db) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches

e. LPCI Pumps B & C Discharge Pressure-High 1,2(db),3(db) 2 per pump G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(ec)

SR 3.3.5.1.4(ec)

SR 3.3.5.1.5 115 psig and 135 psig

f. ADS Drywell Pressure Bypass Timer 1,2(db),3(db) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes

g. Manual Initiation 1,2(db),3(db) 2 G

SR 3.3.5.1.5 NA (db) With reactor steam dome pressure > 150 psig.

(ec) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43a Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.5.2-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel.

Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

B.1 Declare associated penetration flow path(s) incapable of automatic isolation.

AND B.2 Calculate DRAIN TIME.

Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

C.1 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43b Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

D.1 Declare HPCS system inoperable.

OR D.2 Align the HPCS pump suction to the suppression pool.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour E. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

E.1 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. Required Action and associated Completion Time of Condition C, D, or E not met.

F.1 Declare associated ECCS injection/spray subsystem inoperable.

Immediately

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43c Amendment No. 9 5 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------

Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43d Amendment No. 95 Table 3.3.5.2-1 (page 1 of 2)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems

a.

Reactor Vessel Pressure -

Low (Injection Permissive) 4,5 4(a)

C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig

b. LPCS Pump Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 750 gpm

c. LPCI Pump A Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm

2. LPCI B and LPCI C Subsystems
a. Reactor Vessel Pressure - Low (Injection Permissive) 4,5 4(a)

C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig

b. LPCI Pump B and LPCI Pump C Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm (continued)

(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-44 Amendment No.

Table 3.3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. High Pressure Core Spray (HPCS) System
a. RCIC Storage Tank Level - Low 4(b), 5(b) 2(a)

D SR 3.3.5.2.1 SR 3.3.5.2.2 3.0 inches

b. HPCS Pump Discharge Pressure - High (Bypass) 4, 5 1(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 120 psig

c. HPCS System Flow Rate - Low (Bypass) 4, 5 1(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 500 gpm

4. RHR System Isolation
a. Reactor Vessel Water Level -

Low, Level 3 (c) 2 in one trip system B

SR 3.3.5.2.1 SR 3.3.5.2.2 8.3 inches

5. Reactor Water Cleanup (RWCU) System Isolation
a. Reactor Vessel Water Level - Low Low, Level 2 (c) 2 in one trip system B

SR 3.3.5.2.1 SR 3.3.5.2.2

-48.1 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."

(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.

(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-45 Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.23 The RCIC System instrumentation for each Function in Table 3.3.5.23-1 shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.23-1 for the channel.

Immediately B.

As required by Required Action A.1 and referenced in Table 3.3.5.23-1.

B.1 Declare RCIC System inoperable.

AND B.2 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of RCIC initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C.

As required by Required Action A.1 and referenced in Table 3.3.5.23-1.

C.1 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-46 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

As required by Required Action A.1 and referenced in Table 3.3.5.23-1.

D.1

NOTE----------

Only applicable if RCIC pump suction is not aligned to the suppression pool.

Declare RCIC System inoperable.

AND D.2.1 Place channel in trip.

OR D.2.2 Align RCIC pump suction to the suppression pool.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of RCIC initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours E.

Required Action and associated Completion Time of Condition B, C, or D not met.

E.1 Declare RCIC System inoperable.

Immediately

RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-47 Amendment No. 192 SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------

1. Refer to Table 3.3.5.23-1 to determine which SRs apply for each RCIC Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2 and 5; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.23.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.3 Calibrate the analog trip module.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.4 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.23.6 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

RCIC System Instrumentation 3.3.5.32 CLINTON 3.3-48 Amendment No. 169 Table 3.3.5.23-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation FUNCTION REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Reactor Vessel Water Level-Low Low, Level 2 4

B SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.5 SR 3.3.5.23.6

-48.1 inches

2. Reactor Vessel Water Level-High, Level 8 2

C SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5 52.6 inches

3. RCIC Storage Tank Level-Low 2

D SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5 3.0 inches

4. Suppression Pool Water Level-High 2

D SR 3.3.5.23.1 SR 3.3.5.23.2 SR 3.3.5.23.3 SR 3.3.5.23.4 SR 3.3.5.23.5

-5 inches

5. Manual Initiation 1

C SR 3.3.5.23.5 NA

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-49 Amendment No. 95 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1 The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------

Only applicable to Main Steam Line (MSL) isolation Functions.

A. One or more Functions with one channel inoperable.

A.1 Place one channel in affected Function in trip.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

NOTE----------

Only applicable to MSL isolation Functions.

B.

One or more Functions with two channels inoperable.

B.1 Place one channel in affected Function in trip.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

NOTE----------

Only applicable to MSL isolation Functions.

C. One or more Functions with three or more channels inoperable.

C.1 Restore two channels in affected Function to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-50 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------

Not applicable to MSL isolation Functions.

D. One or more required channels inoperable.

D.1 Place channel in trip.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

NOTE---------

Not applicable to MSL isolation Functions.

E. One or more automatic Functions with isolation capability not maintained.

E.1 Restore isolation capability.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.

F.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.

Immediately G. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

G.1 Isolate associated MSL.

OR G.2.1 Be in MODE 3.

AND G.2.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

H.1 Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

I.1 Isolate the affected penetration flow path(s).

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-51 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

J.1 Isolate the affected penetration flow path(s).

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> K. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

OR Required Action and associated Completion Time of Condition I or J not met.

K.1 Be in MODE 3.

AND K.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours L. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

L.1 Declare associated standby liquid control subsystem inoperable.

OR L.2 Isolate the Reactor Water Cleanup System.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour M. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

M.1 Initiate action to restore channel to OPERABLE status.

OR M.2 Initiate action to isolate the Residual Heat Removal (RHR)

Shutdown Cooling System suction from the reactor vessel.

OR Immediately Immediately (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-52 Amendment No. 95 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M.

(Continued)

M.3.1 Initiate action to restore secondary containment to OPERABLE status.

AND M.3.2 Initiate action to restore one standby gas treatment (SGT) subsystem to OPERABLE status.

AND M.3.3 Initiate action to restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.

AND M.3.4

NOTE-------

Entry and exit is permissible under administrative control.

Initiate action to close one door in the upper containment personnel air lock.

Immediately Immediately Immediately Immediately N.

As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

N.1 Isolate the affected penetration flow path(s).

OR N.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND N.2.2 Initiate action to suspend operations with a potential for draining the reactor vessel.

Immediately Immediately Immediately (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-53 Amendment No. 192 CONDITION REQUIRED ACTION COMPLETION TIME O.

As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

O.1 Isolate the affected penetration flow path(s).

OR O.2 Initiate action to suspend operations with a potential for draining the reactor vessel.

Immediately Immediately SURVEILLANCE REQUIREMENTS

NOTES------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Calibrate the analog trip module.

In accordance with the Surveillance Frequency Control Program (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-54 Amendment No. 192 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7

NOTE---------------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME for the main steam isolation valves is within limits.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-55 Amendment No. 169 Table 3.3.6.1-1 (page 1 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line Isolation
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8

-148.1 inches

b. Main Steam Line Pressure-Low 1

4 H

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 841 psig

c. Main Steam Line Flow-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 284 psid

d. Condenser Vacuum-Low 1,2(a),

3(a) 4 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7.6 inches Hg vacuum

e. Main Steam Tunnel Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

f. Main Steam Line Turbine Building Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 Modules 1-4 142°F, Module 5 150°F

g. Manual Initiation 1,2,3 4

J SR 3.3.6.1.6 NA (continued)

(a) With any turbine stop valve not closed.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-56 Amendment No. 169 Table 3.3.6.1-1 (page 2 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. Primary Containment and Drywell Isolation
a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 (c) 4(b) 4 K

O SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

-48.1 inches

b. Drywell Pressure-High 1,2,3 4(b)

K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

c. Deleted
d. Drywell Pressure-High (ECCS Divisions 1 and 2) 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

e. Reactor Vessel Water Level-Low Low, Level 2 (HPCS NSPS Div 3 and 4) 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

f. Drywell Pressure-High (HPCS NSPS Div 3 and
4) 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig (continued)

(b) Also required to initiate the associated drywell isolation function.

(c) During operations with a potential for draining the reactor vessel.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-57 Amendment No. 169 Table 3.3.6.1-1 (page 3 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. Primary Containment and Drywell Isolation (continued)
g. Containment Building Fuel Transfer Pool Ventilation Plenum Radiation-High (c),(dc) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 500 mR/hr

h. Containment Building Exhaust Radiation-High 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c),(dc) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr

i. Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c),(dc) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr

j. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-148.1 inches (c) 4 O

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.86

-148.1 inches

k. Containment Pressure-High (ed) 2 I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 3.0 psid

l. Manual Initiation 1,2,3 2(b)

J SR 3.3.6.1.6 NA (c)(dc) 2 N

SR 3.3.6.1.6 NA (continued)

(b) Also required to initiate the associated drywell isolation function.

(c) During operations with a potential for draining the reactor vessel.

(dc) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

(ed) MODES 1, 2, and 3 with the associated PCIVs not closed.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-58 Amendment No. 169 Table 3.3.6.1-1 (page 4 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. Reactor Core Isolation Cooling (RCIC) System Isolation
a. Auxiliary Building RCIC Steam Line Flow-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 118.5 inches water

b. RCIC Steam Line Flow-High, Time Delay 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 13 seconds

c. RCIC Steam Supply Line Pressure-Low 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 52 psig

d. RCIC Turbine Exhaust Diaphragm Pressure-High 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 20 psig

e. RCIC Equipment Room Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 207°F

f. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

g. Main Steam Line Tunnel Temperature Timer 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 28 minutes

h. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

i. Drywell RCIC Steam Line Flow - High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188 inches water (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-59 Amendment No. 169 Table 3.3.6.1-1 (page 5 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3.

RCIC System Isolation (continued)

j. Drywell Pressure - High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

k. Manual Initiation 1,2,3 1

J SR 3.3.6.1.6 NA

4. Reactor Water Cleanup (RWCU) System Isolation
a. Differential Flow -

High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8 66.1 gpm

b. Differential Flow-Timer 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 47 seconds

c. RWCU Heat Exchanger Equipment Room Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 205°F

d. RWCU Pump Rooms Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 202°F

e. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

f. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches (c) 4 O

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.56 SR 3.3.6.1.68

-48.1 inches

g. Standby Liquid Control System Initiation 1,2,3 2

L SR 3.3.6.1.6 NA

h. Manual Initiation 1,2,3 (c),(dc) 2 2

J N

SR 3.3.6.1.6 SR 3.3.6.1.6 NA NA (continued)

(c) During operations with a potential for draining the reactor vessel.

(dc)

During movement of recently irradiated fuel assemblies in the primary or secondary containment.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-60 Amendment No. 169 Table 3.3.6.1-1 (page 6 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. RHR System Isolation
a. RHR Heat Exchanger Ambient Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 160°F

b. Reactor Vessel Water Level - Low, Level 3 1,2,3(fe) 4 I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches

c. Reactor Vessel Water Level - Low, Level 3 3(gf),4,5 4(h)

M SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches

d. Reactor Vessel Water Level - Low Low Low, Level 1 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-148.1 inches

e. Reactor Vessel Pressure-High 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 113 psig

f. Drywell Pressure-High 1,2,3 8

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

g. Manual Initiation 1,2,3 2

J SR 3.3.6.1.6 NA (fe) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.

(gf) With reactor steam dome pressure less than the RHR cut in permissive pressure.

(h) Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.

Secondary Containment Isolation Instrumentation 3.3.6.2 CLINTON 3.3-64 Amendment No. 169 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Reactor Vessel Water Level-Low Low, Level 2 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6

-48.1 inches

2.

Drywell Pressure-High 1,2,3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 1.88 psig

3.

Containment Building Fuel Transfer Pool Ventilation Plenum Exhaust Radiation-High (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 500 mR/hr

4.

Containment Building Exhaust Radiation-High 1,2,3,(a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr

5.

Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3, (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr

6.

Fuel Building Exhaust Radiation-High 1,2,3, (cb) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 17 mR/hr

7.

Manual Initiation 1,2,3, (a),(b) 1 SR 3.3.6.2.5 NA (a) During operations with a potential for draining the reactor vessel.

(ba) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

(cb) During movement of recently irradiated fuel assemblies in the fuel building.

Control Room Ventilation System Instrumentation 3.3.7.1 CLINTON 3.3-77 Amendment No. 152 Table 3.3.7.1-1 (page 1 of 1)

Control Room Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Control Room Air Intake Radiation Monitors 1,2,3, (a),(b) 1/Intake SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 26 mR/hr (a) During operations with a potential for draining the reactor vessel.

(ba) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.

ECCS Operating 3.5.1 CLINTON 3.5-1 Amendment No. 163 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.1 ECCS Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/

relief valves shall be OPERABLE.

NOTE----------------------------

One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.

APPLICABILITY:

MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS

NOTE-------------------------------------

LCO 3.0.4.b is not applicable to HPCS.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.

A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.

7 days B. High Pressure Core Spray (HPCS) System inoperable.

B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.

AND B.2 Restore HPCS System to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 14 days (continued)

ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-6 Amendment No. 133 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS  ShutdownRPV Water Inventory Control LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND Two One ECCS injection/spray subsystems shall be OPERABLE.

NOTE----------------------------One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.

APPLICABILITY:

MODES 4 and, MODE 5 except with the reactor cavity to steam dryer pool gate removed and water level  22 ft 8 inches over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

ROne required ECCS injection/spray subsystem inoperable.

A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.suspend operations with a potential for draining the reactor vessel (OPDRVs).

Immediately C.

Two required ECCS injection/spray subsystems inoperable.

C.1 Initiate action to suspend OPDRVs.

AND C.2 Restore one ECCS injection/spray subsystem to OPERABLE status.

Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)

ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-7 Amendment No. 133 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C.1 Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.

AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)

ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-8 Amendment No. 133 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Required Action C.2 and associated Completion Time not met.

D.1

NOTE --------

Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.

Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND D.2 Initiate action to restore establish secondary containment to OPERABLE statusboundary.

AND D.23 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.

Initiate action to restore one standby gas treatment subsystem to OPERABLE status.

AND D.34 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

AND D.4

NOTE--------

Entry and exit is permissible under administrative control.

Initiate action to close one door in the upper containment personnel air lock.

Immediately Immediately Immediately Immediately (continued)

ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-9 Amendment No. 204 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.

OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

E.1 Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.12 Verify, for each a required low pressure ECCS injection/spray subsystem, the suppression pool water level is 12 ft 8 inches.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.23 Verify, for the a required High Pressure Core Spray (HPCS) System, the:

a.

Suppression pool water level is 12 ft 8 inches; or

b.

RCIC storage tank available water volume is 125,000 gal.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.34 Verify, for each the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program (continued)

ECCS ShutdownRPV Water Inventory Control 3.5.2 CLINTON 3.5-10 Amendment No. 204 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.45

NOTES-----------------

1. One low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system vent flow paths opened under administrative control.

Verify, each for the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.56 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.Verify each required ECCS pump develops the specified flow rate with the specified pump differential pressure.

PUMP DIFFERENTIAL SYSTEM FLOW RATE PRESSURE LPCS 5010 gpm 290 psid LPCI 5050 gpm 113 psid HPCS 5010 gpm 363 psid In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.68

NOTE--------------------

Vessel injection/spray may be excluded.

Verify each the required ECCS injection/spray subsystem can be manually operated.actuates on an actual or simulated automatic initiation signal.

In Accordance with the Surveillance Frequency Control Program

RCIC System 3.5.3 CLINTON 3.5-11 Amendment No. XXX 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE-------------------------------------

LCO 3.0.4.b is not applicable to RCIC.

CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

A.1 Verify by administrative means High Pressure Core Spray System is OPERABLE.

AND A.2 Restore RCIC System to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 14 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Reduce reactor steam dome pressure to 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program (continued)

RCIC System 3.5.3 CLINTON 3.5-12 Amendment No. XXX SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.2

NOTE--------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.3

NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with RCIC steam supply pressure 1045 psig and 920 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.4

NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with RCIC steam supply pressure 150 psig and 135 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.5

NOTE--------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program

Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-3 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 Each primary containment air lock shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3,

NOTE------------------------------

The following Applicabilityies appliesy only to the upper containment personnel air lock.

During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES------------------------------------

1. Entry and exit is permissible to perform repairs of the affected air lock components.
2. Separate Condition entry is allowed for each air lock.
3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.

(continued)

Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-7 Amendment No. 147 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition A, B, or C not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or OPDRVs.

NOTE------------

LCO 3.0.3 is not applicable.

E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

AND E.2 Initiation action to suspend OPDRVs.

Immediately Immediately

PCIVs 3.6.1.3 CLINTON 3.6-9 Amendment No. 158 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, MODES 4 and 5 for RHR Shutdown Cooling System suction from the reactor vessel isolation valves when associated isolation instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment and Drywell Isolation Instrumentation," Function 5.c.

NOTE------------------------------

The following Applicabilityies apply applies only to secondary containment bypass leakage isolation valves.

During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.

(continued)

PCIVs 3.6.1.3 CLINTON 3.6-14 Amendment No. 147 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)

D.3 Perform SR 3.6.1.3.5 for the resilient seal purge valves closed to comply with Required Action D.1.

Once per 92 days E. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during movement of recently irradiated fuel assemblies in the primary or secondary containment.

F.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in primary and secondary containment.

Immediately G. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during MODE 4 or 5 or during OPDRVs.

G.1 Initiate action to suspend OPDRVs.

OR G.2 Initiate action to restore valve(s) to OPERABLE status.

Immediately Immediately (continued)

Secondary Containment 3.6.4.1 CLINTON 3.6-43 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment inoperable in MODE 1, 2, or 3.

A.1 Restore secondary containment to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.

Required Action and associated Completion Time of Condition A not met.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Secondary Containment 3.6.4.1 CLINTON 3.6-44 Amendment No. 192 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.

C.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

AND C.2 Initiate action to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.

In accordance with the Surveillance Frequency Control Program (continued)

SCIDs 3.6.4.2 CLINTON 3.6-47 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)

LCO 3.6.4.2 Each SCID shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.

(continued)

SCIDs 3.6.4.2 CLINTON 3.6-49 Amendment No. 147 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.

D.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

AND D.2 Initiate action to suspend OPDRVs.

Immediately Immediately

SGT System 3.6.4.3 CLINTON 3.6-51 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.

A.1 Restore SGT subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

SGT System 3.6.4.3 CLINTON 3.6-52 Amendment No. 187 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.

NOTE------------

LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR C.2.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

AND C.2.2 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately D.

Two SGT subsystems inoperable in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

D.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

SGT System 3.6.4.3 CLINTON 3.6-53 Amendment No. 201 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment, or during OPDRVs.

E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

AND E.2 Initiate action to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes with heaters operating.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling bypass damper can be opened and the fan started.

In accordance with the Surveillance Frequency Control Program

Control Room Ventilation System 3.7.3 CLINTON 3.7-4 Amendment No. 95 3.7 PLANT SYSTEM 3.7.3 Control Room Ventilation System LCO 3.7.3 Two Control Room Ventilation subsystems shall be OPERABLE.

NOTE---------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Control Room Ventilation subsystem inoperable for reasons other than Condition C.

A.1 Restore Control Room Ventilation subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.

C.1 Initiate action to implement mitigating actions.

AND C.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND C.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days (continued)

Control Room Ventilation System 3.7.3 CLINTON 3.7-5 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and Associated Completion Time of Condition C not met in MODE 1, 2, or 3.

D.1 Be in MODE 3.

AND D.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours E. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.

NOTE-------------

LCO 3.0.3 is not applicable.

E.1 Place OPERABLE Control Room Ventilation subsystem in high radiation mode.

OR E.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND E.2.2 Suspend CORE ALTERATIONS.

AND E.2.3 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately Immediately F. Two Control Room Ventilation subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition C.

NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE 3.

F.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Control Room Ventilation System 3.7.3 CLINTON 3.7-6 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two Control Room Ventilation subsystems inoperable during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.

OR One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.

G.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND G.2 Suspend CORE ALTERATIONS.

AND G.3 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each Control Room Ventilation subsystem with flow through the makeup filter for 15 continuous minutes with the heaters operating.

In accordance with the Surveillance Frequency Control Program SR 3.7.3.2 Operate each Control Room Ventilation subsystem with flow through the recirculation filter for 15 minutes.

In accordance with the Surveillance Frequency Control Program (continued)

Control Room AC System 3.7.4 CLINTON 3.7-8 Amendment No. 95 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC subsystem inoperable.

A.1 Restore control room AC subsystem to OPERABLE status.

30 days B. Two control room AC subsystems inoperable.

B.1 Verify control room area temperature 86 ºF.

AND B.2 Restore one control room AC subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 7 days C. Required Action and Associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Control Room AC System 3.7.4 CLINTON 3.7-9 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.

NOTE-------------

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE control room AC subsystem in operation.

OR D.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND D.2.2 Suspend CORE ALTERATIONS.

AND D.2.3 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately Immediately (continued)

Control Room AC System 3.7.4 CLINTON 3.7-10 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition B not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS, or during OPDRVs.

NOTE-------------

LCO 3.0.3 is not applicable.

E.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND E.2 Suspend CORE ALTERATIONS.

AND E.3 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the capability to remove the assumed heat load.

In accordance with the Surveillance Frequency Control Program

AC Sources Shutdown 3.8.2 CLINTON 3.8-16 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";

b.

One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and

c.

One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTE----------------------------------

LCO 3.0.3 is not applicable.

(continued)

AC Sources Shutdown 3.8.2 CLINTON 3.8-17 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO Item a not met.

NOTE-------------

Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.

A.1 Declare affected required feature(s) with no offsite power available from a required circuit inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.43 Initiate action to restore required offsite power circuit to OPERABLE status.

Immediately Immediately Immediately Immediately Immediately (continued)

AC Sources Shutdown 3.8.2 CLINTON 3.8-18 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. LCO Item b not met.

B.1 Suspend CORE ALTERATIONS.

AND B.2 Suspend movement of irradiated fuel assemblies in primary and secondary containment.

AND B.3 Initiate action to suspend OPDRVs.

AND B.43 Initiate action to restore required DG to OPERABLE status.

Immediately Immediately Immediately Immediately C. LCO Item c not met.

C.1 Declare High Pressure Core Spray System inoperable.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

DC Sources Shutdown 3.8.5 CLINTON 3.8-27 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 The following shall be OPERABLE:

a.

One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -

Shutdown";

b.

One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and

c.

The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTE-------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One battery charger on one division inoperable.

A.1 Restore battery terminal voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify battery float current < 2 amps.

AND A.3 Restore battery charger to OPERABLE status.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 7 days (continued)

DC Sources Shutdown 3.8.5 CLINTON 3.8-28 Amendment No. 142 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required DC electrical power subsystems inoperable for reasons other than Condition A.

OR Required Action and associated Completion Time of Condition A not met.

B.1 Declare affected required feature(s) inoperable.

OR B.2.1 Suspend CORE ALTERATIONS.

AND Immediately Immediately B.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND Immediately B.2.3 Initiate action to suspend operations with a potential for draining the reactor.

Immediately AND B.2.43 Initiate action to restore required DC electrical power subsystems to OPERABLE status.

Immediately

Inverters-Shutdown 3.8.8 CLINTON 3.8-36 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters Shutdown LCO 3.8.8 The following Divisional inverters shall be OPERABLE:

a.

One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b.

The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, ECCS-ShutdownRPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

Inverters Shutdown 3.8.8 CLINTON 3.8-37 Amendment No. 95 ACTIONS

NOTE-------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required divisional inverters inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND Immediately Immediately A.2.2 Suspend handling of irradiated fuel assemblies in the primary and secondary containment.

AND Immediately A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND Immediately A.2.43 Initiate action to restore required divisional inverters to OPERABLE status.

Immediately

Distribution Systems Shutdown 3.8.10 CLINTON 3.8-43 Amendment No. 192 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND A.2.43 Initiate actions to restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.

AND A.2.54 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.

Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and uninterruptible AC bus electrical power distribution subsystems.

In accordance with the Surveillance Frequency Control Program

Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 3 REVISED TECHNICAL SPECIFICATIONS PAGES TOC Page ii TOC Page iii TOC Page iv 1.0-1 1.0-2 1.0-3 1.0-4 1.0-5 3.3-32 3.3-33 3.3-35 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-45 3.3-46 3.3-47 3.3-48 3.3-49 3.3-50 3.3-51 3.3-52 3.3-53 3.3-54 3.3-55 3.3-56 3.3-57 3.3-58 3.3-59 3.3-60 3.3-64 3.3-77 3.5-1 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 3.6-3 3.6-7 3.6-9 3.6-14 3.6-43 3.6-44 3.6-47 3.6-49 3.6-51 3.6-52 3.6-53 3.7-4 3.7-5 3.7-6 3.7-8 3.7-9 3.7-10 3.8-16 3.8-17 3.8-18 3.8-27 3.8-28 3.8-36 3.8-37 3.8-43

TABLE OF CONTENTS CLINTON Revision No. 14-2 ii 3.2 POWER DISTRIBUTION LIMITS (continued) 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)...........................3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)...........................3.2-3 B 3.2 POWER DISTRIBUTION LIMITS.....................................B 3.2-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)..................................................B 3.2-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)...........................B 3.2-5 B 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)............................B 3.2-9 3.3 INSTRUMENTATION...............................................3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation...........3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation................3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation....3.3-14a 3.3.2.1 Control Rod Block Instrumentation.........................3.3-15 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation............3.3-19 3.3.3.2 Remote Shutdown System....................................3.3-23 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation.......................................3.3-25 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation..................3.3-28 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......3.3-31 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation................................... 3.3-43a 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation................................... 3.3-44 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.3.3-48 3.3.6.2 Secondary Containment Isolation Instrumentation...........3.3-61 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation.......................................3.3-65 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....3.3-69 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............3.3-74 3.3.7.1 Control Room Ventilation System Instrumentation...........3.3-75 3.3.8.1 Loss of Power (LOP) Instrumentation.......................3.3-78 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.3.3-81 B 3.3 INSTRUMENTATION............................................. B 3.3-1 B 3.3.1.1 Reactor Protection System (RPS) Instrumentation......... B 3.3-1 B 3.3.1.2 Source Range Monitor (SRM) Instrumentation.............. B 3.3-31 B 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation.. B 3.3-39a B 3.3.2.1 Control Rod Block Instrumentation....................... B 3.3-40 B 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation.......... B 3.3-49 (continued)

TABLE OF CONTENTS CLINTON Revision No. 2-13 iii B 3.3 INSTRUMENTATION (continued)

B 3.3.3.2 Remote Shutdown System....................................B 3.3-60 B 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation...........................................B 3.3-65 B 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation........B 3.3-76 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......B 3.3-85 B 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation...................................... B 3.3-122a B 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................... B 3.3-123 B 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation.........................B 3.3-135 B 3.3.6.2 Secondary Containment Isolation Instrumentation...........B 3.3-174 B 3.3.6.3 Residual Heat Removal (RHR) Containment Spray System Instrumentation...........................................B 3.3-186 B 3.3.6.4 Suppression Pool Makeup (SPMU) System Instrumentation.....B 3.3-197 B 3.3.6.5 Relief and Low-Low Set (LLS) Instrumentation..............B 3.3-208 B 3.3.7.1 Control Room Ventilation (CRV) System Instrumentation.....B 3.3-215 B 3.3.8.1 Loss of Power (LOP) Instrumentation.......................B 3.3-222 B 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.....................................B 3.3-230 3.4 REACTOR COOLANT SYSTEM (RCS)..................................3.4-1 3.4.1 Recirculation Loops Operating.............................3.4-1 3.4.2 Flow Control Valves (FCVs)................................3.4-6 3.4.3 Jet Pumps.................................................3.4-8 3.4.4 Safety/Relief Valves (S/RVs)..............................3.4-10 3.4.5 RCS Operational LEAKAGE...................................3.4-12 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................3.4-14 3.4.7 RCS Leakage Detection Instrumentation.....................3.4-17 3.4.8 RCS Specific Activity.....................................3.4-20 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown......................................3.4-22 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.....................................3.4-25 3.4.11 RCS Pressure and Temperature (P/T) Limits.................3.4-27 3.4.12 Reactor Steam Dome Pressure...............................3.4-33 B 3.4 REACTOR COOLANT SYSTEM (RCS)..................................B 3.4-1 B 3.4.1 Recirculation Loops Operating.............................B 3.4-1 B 3.4.2 Flow Control Valves (FCVs)................................B 3.4-9 (continued)

TABLE OF CONTENTS CLINTON Revision No. 14-2 iv B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

B 3.4.3 Jet Pumps.................................................B 3.4-13 B 3.4.4 Safety/Relief Valves (S/RVs)..............................B 3.4-17 B 3.4.5 RCS Operational LEAKAGE...................................B 3.4-23 B 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage................B 3.4-28 B 3.4.7 RCS Leakage Detection Instrumentation.....................B 3.4-33 B 3.4.8 RCS Specific Activity.....................................B 3.4-39 B 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown..................................B 3.4-43 B 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................B 3.4-48 B 3.4.11 RCS Pressure and Temperature (P/T) Limits.................B 3.4-53 B 3.4.12 Reactor Steam Dome Pressure...............................B 3.4-63 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................3.5-1 3.5.1 ECCS - Operating...........................................3.5-1 3.5.2 RPV Water Inventory Control...............................3.5-6 3.5.3 RCIC System...............................................3.5-11 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.........................................B 3.5-1 B 3.5.1 ECCS - Operating...........................................B 3.5-1 B 3.5.2 RPV Water Inventory Control...............................B 3.5-17 B 3.5.3 RCIC System...............................................B 3.5-27 3.6 CONTAINMENT SYSTEMS...........................................3.6-1 3.6.1.1 Primary Containment.......................................3.6-1 3.6.1.2 Primary Containment Air Locks.............................3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs)..............3.6-9 3.6.1.4 Primary Containment Pressure..............................3.6-20 3.6.1.5 Primary Containment Air Temperature.......................3.6-21 3.6.1.6 Low-Low Set (LLS) Valves..................................3.6-22 3.6.1.7 Residual Heat Removal (RHR) Containment Spray System......3.6-24 3.6.1.8 Deleted...................................................3.6-26 3.6.1.9 Feedwater Leakage Control System (FWLCS)..................3.6-27a 3.6.2.1 Suppression Pool Average Temperature......................3.6-28 3.6.2.2 Suppression Pool Water Level..............................3.6-31 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling......3.6-32 3.6.2.4 Suppression Pool Makeup (SPMU) System.....................3.6-34 3.6.3.1 Deleted.................................................3.6-36 3.6.3.2 Primary Containment and Drywell Hydrogen Igniters.........3.6-38 (continued)

Definitions 1.1 CLINTON 1.0-1 Amendment No. 105 1.0 USE AND APPLICATION 1.1 Definitions

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR)

LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

(continued)

Definitions 1.1 CLINTON 1.0-2 Amendment No. 105 1.1 Definitions (continued)

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel,sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, ORNL, 1989.

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a.

The water inventory above the TAF is divided by the limiting drain rate;

b.

The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g.,

seismic event, loss of normal power, single human error), for all (continued)

Definitions 1.1 CLINTON 1.0-3 Amendment No. 105 Definitions DRAIN TIME penetration flow paths below the TAF except:

(continued)

1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation devices without offsite power.
c. The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;
d. No additional draining events occur; and
e. Realistic cross-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

Definitions 1.1 CLINTON 1.0-4 Amendment No. 105 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE associated turbine stop valve or turbine TIME control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE
1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;
b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;
c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

(continued)

Definitions 1.1 CLINTON 1.0-5 Amendment No. 95 128 1.1 Definitions (continued)

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3473 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-32 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

B.1

NOTE---------

Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions B.2

NOTE---------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure Core Spray (HPCS)

System inoperable.

AND B.3 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-33 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

C.1

NOTE--------

Only applicable for Functions 1.c, 1.d, 2.c, and 2.d.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions C.2 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-35 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

E.1

NOTE---------

Only applicable for Functions 1.e, 1.f, and 2.e.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND E.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions 7 days (continued)

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-39 Amendment No. 169 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems

a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 2(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c)

-148.1 inches

b. Drywell Pressure-High 1,2,3 2(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. LPCI Pump A Start-Time Delay Logic Card 1,2,3 1

C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds

d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 454 psig and 494 psig

e. LPCS Pump Discharge Flow-Low (Bypass) 1,2,3 1

E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 750 gpm

f. LPCI Pump A Discharge Flow-Low (Bypass) 1,2,3 1

E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm

g. Manual Initiation 1,2,3 1

C SR 3.3.5.1.5 NA (continued)

(a) Also required to initiate the associated diesel generator.

(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-40 Amendment No. 169 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. LPCI B and LPCI C Subsystems
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 2(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c)

-148.1 inches

b. Drywell Pressure-High 1,2,3 2(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. LPCI Pump B Start-Time Delay Logic Card 1,2,3 1

C SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4.5 seconds and 5.5 seconds

d. Reactor Vessel Pressure-Low (Injection Permissive) 1,2,3 4

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 454 psig and 494 psig

e. LPCI Pump B and LPCI Pump C Discharge Flow-Low (Bypass) 1,2,3 1 per pump E

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 900 gpm

f. Manual Initiation 1,2,3 1

C SR 3.3.5.1.5 NA (continued)

(a) Also required to initiate the associated diesel generator.

(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-41 Amendment No. 169 Table 3.3.5.1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. High Pressure Core Spray (HPCS) System
a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c)

-48.1 inches

b. Drywell Pressure - High 1,2,3 4(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. Reactor Vessel Water Level-High, Level 8 1,2,3 2

C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c) 54.6 inches

d. RCIC Storage Tank Level-Low 1,2,3 2

D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 3.0 inches

e. Suppression Pool Water Level-High 1,2,3 2

D SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 11 inches

f. HPCS Pump Discharge Pressure-High (Bypass) 1,2,3 1

E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 120 psig

g. HPCS System Flow Rate-Low (Bypass) 1,2,3 1

E SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 500 gpm

h. Manual Initiation 1,2,3 1

C SR 3.3.5.1.5 NA (continued)

(a) Also required to initiate the associated diesel generator.

(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-42 Amendment No. 169 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

4. Automatic Depressurization System (ADS) Trip System 1 (Logic A and E)
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c)

-148.1 inches

b. Drywell Pressure-High 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. ADS Initiation Timer 1,2(b),3(b) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds

d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches

e. LPCS Pump Discharge Pressure-High 1,2(b),3(b) 2 G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 125 psig and

< 176.3 psig

f. LPCI Pump A Discharge Pressure-High 1,2(b),3(b) 2 G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 115 psig and

< 135 psig

g. ADS Drywell Pressure Bypass Timer 1,2(b),3(b) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes

h. Manual Initiation 1,2(b),3(b) 2 G

SR 3.3.5.1.5 NA (continued)

(b) With reactor steam dome pressure > 150 psig.

(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

ECCS Instrumentation 3.3.5.1 CLINTON 3.3-43 Amendment No. 169 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. ADS Trip System 2 (Logic B and F)
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.5 SR 3.3.5.1.6(c)

-148.1 inches

b. Drywell Pressure-High 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 1.88 psig

c. ADS Initiation Timer 1,2(b),3(b) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 117 seconds

d. Reactor Vessel Water Level-Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 8.3 inches

e. LPCI Pumps B & C Discharge Pressure-High 1,2(b),3(b) 2 per pump G

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3(c)

SR 3.3.5.1.4(c)

SR 3.3.5.1.5 115 psig and 135 psig

f. ADS Drywell Pressure Bypass Timer 1,2(b),3(b) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 6.5 minutes

g. Manual Initiation 1,2(b),3(b) 2 G

SR 3.3.5.1.5 NA (b) With reactor steam dome pressure > 150 psig.

(c) 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined As-Found Tolerance band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

2. The instrument channel setpoint shall be reset to a value within the As-Left Tolerance of the Actual Trip Setpoint; otherwise, the channel shall be declared inoperable.
3. The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined As-Found Tolerance and As-Left Tolerance bands shall be specified in the ORM.

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43a Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.5.2-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel.

Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

B.1 Declare associated penetration flow path(s) incapable of automatic isolation.

AND B.2 Calculate DRAIN TIME.

Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

C.1 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43b Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

D.1 Declare HPCS system inoperable.

OR D.2 Align the HPCS pump suction to the suppression pool.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour E. As required by Required Action A.1 and referenced in Table 3.3.5.2-1.

E.1 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. Required Action and associated Completion Time of Condition C, D, or E not met.

F.1 Declare associated ECCS injection/spray subsystem inoperable.

Immediately

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43c Amendment No. 9 5 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------

Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-43d Amendment No. 95 Table 3.3.5.2-1 (page 1 of 2)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems

a.

Reactor Vessel Pressure -

Low (Injection Permissive) 4,5 4(a)

C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig

b. LPCS Pump Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 750 gpm

c. LPCI Pump A Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm

2. LPCI B and LPCI C Subsystems
a. Reactor Vessel Pressure - Low (Injection Permissive) 4,5 4(a)

C SR 3.3.5.2.1 SR 3.3.5.2.2 494 psig

b. LPCI Pump B and LPCI Pump C Discharge Flow -

Low (Bypass) 4,5 1 per pump(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 900 gpm (continued)

(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."

RPV Water Inventory Control Instrumentation 3.3.5.2 CLINTON 3.3-44 Amendment No.

Table 3.3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. High Pressure Core Spray (HPCS) System
a. RCIC Storage Tank Level - Low 4(b), 5(b) 2(a)

D SR 3.3.5.2.1 SR 3.3.5.2.2 3.0 inches

b. HPCS Pump Discharge Pressure - High (Bypass) 4, 5 1(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 120 psig

c. HPCS System Flow Rate - Low (Bypass) 4, 5 1(a)

E SR 3.3.5.2.1 SR 3.3.5.2.2 500 gpm

4. RHR System Isolation
a. Reactor Vessel Water Level -

Low, Level 3 (c) 2 in one trip system B

SR 3.3.5.2.1 SR 3.3.5.2.2 8.3 inches

5. Reactor Water Cleanup (RWCU) System Isolation
a. Reactor Vessel Water Level - Low Low, Level 2 (c) 2 in one trip system B

SR 3.3.5.2.1 SR 3.3.5.2.2

-48.1 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "RPV Water Inventory Control."

(b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the RCIC storage tank while tank water level is not within the limits of SR 3.5.2.3.

(c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-45 Amendment No. 95 3.3 INSTRUMENTATION 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.3 The RCIC System instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel.

Immediately B.

As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

B.1 Declare RCIC System inoperable.

AND B.2 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of RCIC initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C.

As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

C.1 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)

RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-46 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

D.1

NOTE----------

Only applicable if RCIC pump suction is not aligned to the suppression pool.

Declare RCIC System inoperable.

AND D.2.1 Place channel in trip.

OR D.2.2 Align RCIC pump suction to the suppression pool.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of RCIC initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours E.

Required Action and associated Completion Time of Condition B, C, or D not met.

E.1 Declare RCIC System inoperable.

Immediately

RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-47 Amendment No. 192 SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------

1. Refer to Table 3.3.5.3-1 to determine which SRs apply for each RCIC Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2 and 5; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.3 Calibrate the analog trip module.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.4 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.6 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

RCIC System Instrumentation 3.3.5.3 CLINTON 3.3-48 Amendment No. 169 Table 3.3.5.3-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation FUNCTION REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Reactor Vessel Water Level-Low Low, Level 2 4

B SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.5 SR 3.3.5.3.6

-48.1 inches

2. Reactor Vessel Water Level-High, Level 8 2

C SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5 52.6 inches

3. RCIC Storage Tank Level-Low 2

D SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5 3.0 inches

4. Suppression Pool Water Level-High 2

D SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.3 SR 3.3.5.3.4 SR 3.3.5.3.5

-5 inches

5. Manual Initiation 1

C SR 3.3.5.3.5 NA

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-49 Amendment No. 95 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1 The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------

Only applicable to Main Steam Line (MSL) isolation Functions.

A. One or more Functions with one channel inoperable.

A.1 Place one channel in affected Function in trip.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

NOTE----------

Only applicable to MSL isolation Functions.

B.

One or more Functions with two channels inoperable.

B.1 Place one channel in affected Function in trip.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

NOTE----------

Only applicable to MSL isolation Functions.

C. One or more Functions with three or more channels inoperable.

C.1 Restore two channels in affected Function to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-50 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------

Not applicable to MSL isolation Functions.

D. One or more required channels inoperable.

D.1 Place channel in trip.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

NOTE---------

Not applicable to MSL isolation Functions.

E. One or more automatic Functions with isolation capability not maintained.

E.1 Restore isolation capability.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.

F.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.

Immediately G. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

G.1 Isolate associated MSL.

OR G.2.1 Be in MODE 3.

AND G.2.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

H.1 Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

I.1 Isolate the affected penetration flow path(s).

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-51 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

J.1 Isolate the affected penetration flow path(s).

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> K. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

OR Required Action and associated Completion Time of Condition I or J not met.

K.1 Be in MODE 3.

AND K.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours L. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

L.1 Declare associated standby liquid control subsystem inoperable.

OR L.2 Isolate the Reactor Water Cleanup System.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour M. As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

M.1 Initiate action to restore channel to OPERABLE status.

OR M.2 Initiate action to isolate the Residual Heat Removal (RHR)

Shutdown Cooling System suction from the reactor vessel.

OR Immediately Immediately (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-52 Amendment No. 95 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M.

(Continued)

M.3.1 Initiate action to restore secondary containment to OPERABLE status.

AND M.3.2 Initiate action to restore one standby gas treatment (SGT) subsystem to OPERABLE status.

AND M.3.3 Initiate action to restore isolation capability in each required secondary containment and secondary containment bypass penetration flow path not isolated.

AND M.3.4

NOTE-------

Entry and exit is permissible under administrative control.

Initiate action to close one door in the upper containment personnel air lock.

Immediately Immediately Immediately Immediately N.

As required by Required Action F.1 and referenced in Table 3.3.6.1-1.

N.1 Isolate the affected penetration flow path(s).

OR N.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

Immediately Immediately (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-53 Amendment No. 192 SURVEILLANCE REQUIREMENTS

NOTES------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment and Drywell Isolation Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Calibrate the analog trip module.

In accordance with the Surveillance Frequency Control Program (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-54 Amendment No. 192 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7

NOTE---------------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME for the main steam isolation valves is within limits.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-55 Amendment No. 169 Table 3.3.6.1-1 (page 1 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line Isolation
a. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 SR 3.3.6.1.8

-148.1 inches

b. Main Steam Line Pressure-Low 1

4 H

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 841 psig

c. Main Steam Line Flow-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 284 psid

d. Condenser Vacuum-Low 1,2(a),

3(a) 4 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7.6 inches Hg vacuum

e. Main Steam Tunnel Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

f. Main Steam Line Turbine Building Temperature-High 1,2,3 4

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 Modules 1-4 142°F, Module 5 150°F

g. Manual Initiation 1,2,3 4

J SR 3.3.6.1.6 NA (continued)

(a) With any turbine stop valve not closed.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-56 Amendment No. 169 Table 3.3.6.1-1 (page 2 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. Primary Containment and Drywell Isolation
a. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4(b)

K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

b. Drywell Pressure-High 1,2,3 4(b)

K SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

c. Deleted
d. Drywell Pressure-High (ECCS Divisions 1 and 2) 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

e. Reactor Vessel Water Level-Low Low, Level 2 (HPCS NSPS Div 3 and 4) 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

f. Drywell Pressure-High (HPCS NSPS Div 3 and
4) 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig (continued)

(b) Also required to initiate the associated drywell isolation function.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-57 Amendment No. 169 Table 3.3.6.1-1 (page 3 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. Primary Containment and Drywell Isolation (continued)
g. Containment Building Fuel Transfer Pool Ventilation Plenum Radiation-High (c) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 500 mR/hr

h. Containment Building Exhaust Radiation-High 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr

i. Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr (c) 4 N

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 400 mR/hr

j. Reactor Vessel Water Level-Low Low Low, Level 1 1,2,3 4(b)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-148.1 inches

k. Containment Pressure-High (d) 2 I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 3.0 psid

l. Manual Initiation 1,2,3 2(b)

J SR 3.3.6.1.6 NA (c) 2 N

SR 3.3.6.1.6 NA (continued)

(b) Also required to initiate the associated drywell isolation function.

(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

(d) MODES 1, 2, and 3 with the associated PCIVs not closed.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-58 Amendment No. 169 Table 3.3.6.1-1 (page 4 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. Reactor Core Isolation Cooling (RCIC) System Isolation
a. Auxiliary Building RCIC Steam Line Flow-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 118.5 inches water

b. RCIC Steam Line Flow-High, Time Delay 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 13 seconds

c. RCIC Steam Supply Line Pressure-Low 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 52 psig

d. RCIC Turbine Exhaust Diaphragm Pressure-High 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 20 psig

e. RCIC Equipment Room Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 207°F

f. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

g. Main Steam Line Tunnel Temperature Timer 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 28 minutes

h. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

i. Drywell RCIC Steam Line Flow - High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188 inches water (continued)

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-59 Amendment No. 169 Table 3.3.6.1-1 (page 5 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3.

RCIC System Isolation (continued)

j. Drywell Pressure - High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

k. Manual Initiation 1,2,3 1

J SR 3.3.6.1.6 NA

4. Reactor Water Cleanup (RWCU) System Isolation
a. Differential Flow -

High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.6 SR 3.3.6.1.8 66.1 gpm

b. Differential Flow-Timer 1,2,3 2

I SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 47 seconds

c. RWCU Heat Exchanger Equipment Room Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 205°F

d. RWCU Pump Rooms Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 202°F

e. Main Steam Line Tunnel Ambient Temperature-High 1,2,3 2

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 171°F

f. Reactor Vessel Water Level-Low Low, Level 2 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-48.1 inches

g. Standby Liquid Control System Initiation 1,2,3 2

L SR 3.3.6.1.6 NA

h. Manual Initiation 1,2,3 (c) 2 2

J N

SR 3.3.6.1.6 SR 3.3.6.1.6 NA NA (continued)

(c) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CLINTON 3.3-60 Amendment No. 169 Table 3.3.6.1-1 (page 6 of 6)

Primary Containment and Drywell Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. RHR System Isolation
a. RHR Heat Exchanger Ambient Temperature-High 1,2,3 2 per room I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 160°F

b. Reactor Vessel Water Level - Low, Level 3 1,2,3(e) 4 I

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches

c. Reactor Vessel Water Level - Low, Level 3 3(f) 4 M

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 8.3 inches

d. Reactor Vessel Water Level - Low Low Low, Level 1 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.8

-148.1 inches

e. Reactor Vessel Pressure-High 1,2,3 4

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 113 psig

f. Drywell Pressure-High 1,2,3 8

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 1.88 psig

g. Manual Initiation 1,2,3 2

J SR 3.3.6.1.6 NA (e) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.

(f) With reactor steam dome pressure less than the RHR cut in permissive pressure.

Secondary Containment Isolation Instrumentation 3.3.6.2 CLINTON 3.3-64 Amendment No. 169 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Reactor Vessel Water Level-Low Low, Level 2 1,2,3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6

-48.1 inches

2.

Drywell Pressure-High 1,2,3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5 1.88 psig

3.

Containment Building Fuel Transfer Pool Ventilation Plenum Exhaust Radiation-High (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 500 mR/hr

4.

Containment Building Exhaust Radiation-High 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr

5.

Containment Building Continuous Containment Purge (CCP) Exhaust Radiation-High 1,2,3,(a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 400 mR/hr

6.

Fuel Building Exhaust Radiation-High 1,2,3,(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 17 mR/hr

7.

Manual Initiation 1,2,3,(a) 1 SR 3.3.6.2.5 NA (a) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

(b) During movement of recently irradiated fuel assemblies in the fuel building.

Control Room Ventilation System Instrumentation 3.3.7.1 CLINTON 3.3-77 Amendment No. 152 Table 3.3.7.1-1 (page 1 of 1)

Control Room Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Control Room Air Intake Radiation Monitors 1,2,3,(a) 1/Intake SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 26 mR/hr (a)

During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.

ECCS Operating 3.5.1 CLINTON 3.5-1 Amendment No. 163 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.1 ECCS Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of seven safety/

relief valves shall be OPERABLE.

NOTE----------------------------

One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.

APPLICABILITY:

MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS

NOTE-------------------------------------

LCO 3.0.4.b is not applicable to HPCS.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.

A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.

7 days B. High Pressure Core Spray (HPCS) System inoperable.

B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.

AND B.2 Restore HPCS System to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 14 days (continued)

RPV Water Inventory Control 3.5.2 CLINTON 3.5-6 Amendment No. 133 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.2 RPV Water Inventory Control LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND One ECCS injection/spray subsystem shall be OPERABLE.

NOTE----------------------------

One low pressure coolant injection (LPCI) subsystem may be inoperable during alignment and operation for decay heat removal with reactor steam dome pressure less than the residual heat removal cut in permissive pressure.

APPLICABILITY:

MODES 4 and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS injection/spray subsystem inoperable.

A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.

Immediately (continued)

RPV Water Inventory Control 3.5.2 CLINTON 3.5-7 Amendment No. 133 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C.1 Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.

AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)

RPV Water Inventory Control 3.5.2 CLINTON 3.5-8 Amendment No. 133 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

D.1

NOTE --------

Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.

Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND D.2 Initiate action to establish secondary containment boundary.

AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.

AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

Immediately Immediately Immediately Immediately (continued)

RPV Water Inventory Control 3.5.2 CLINTON 3.5-9 Amendment No. 204 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.

OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

E.1 Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.2 Verify, for a required low pressure ECCS injection/spray subsystem, the suppression pool water level is 12 ft 8 inches.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.3 Verify, for a required High Pressure Core Spray (HPCS) System, the:

a.

Suppression pool water level is 12 ft 8 inches; or

b.

RCIC storage tank available water volume is 125,000 gal.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program (continued)

RPV Water Inventory Control 3.5.2 CLINTON 3.5-10 Amendment No. 204 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.5

NOTE-------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify, for the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.6 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.8

NOTE--------------------

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray subsystem can be manually operated.

In Accordance with the Surveillance Frequency Control Program

RCIC System 3.5.3 CLINTON 3.5-11 Amendment No. XXX 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE-------------------------------------

LCO 3.0.4.b is not applicable to RCIC.

CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

A.1 Verify by administrative means High Pressure Core Spray System is OPERABLE.

AND A.2 Restore RCIC System to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 14 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Reduce reactor steam dome pressure to 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program (continued)

RCIC System 3.5.3 CLINTON 3.5-12 Amendment No. XXX SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.2

NOTE--------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.3

NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with RCIC steam supply pressure 1045 psig and 920 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.4

NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with RCIC steam supply pressure 150 psig and 135 psig, the RCIC pump can develop a flow rate 600 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.5

NOTE--------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program

Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-3 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 Each primary containment air lock shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3,

NOTE------------------------------

The following Applicability applies only to the upper containment personnel air lock.

During movement of recently irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTES------------------------------------

1. Entry and exit is permissible to perform repairs of the affected air lock components.
2. Separate Condition entry is allowed for each air lock.
3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.

(continued)

Primary Containment Air Locks 3.6.1.2 CLINTON 3.6-7 Amendment No. 147 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition A, B, or C not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.

NOTE------------

LCO 3.0.3 is not applicable.

E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

Immediately

PCIVs 3.6.1.3 CLINTON 3.6-9 Amendment No. 158 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3,

NOTE------------------------------

The following Applicability applies only to secondary containment bypass leakage isolation valves.

During movement of recently irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTES------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.
5. Not applicable for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water is maintained el. 753 ft., the steam dryer pool to reactor cavity pool gate is installed with the seal inflated and a backup air supply provided, the total time the flange is open does not exceed 40 days per operating cycle, and the IFTS transfer tube drain valve(s) remain(s) closed, except that the IFTS tube drain valve(s) may be opened under administrative controls.

(continued)

PCIVs 3.6.1.3 CLINTON 3.6-14 Amendment No. 147 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)

D.3 Perform SR 3.6.1.3.5 for the resilient seal purge valves closed to comply with Required Action D.1.

Once per 92 days E. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during movement of recently irradiated fuel assemblies in the primary or secondary containment.

F.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in primary and secondary containment.

Immediately

Secondary Containment 3.6.4.1 CLINTON 3.6-43 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment inoperable in MODE 1, 2, or 3.

A.1 Restore secondary containment to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.

Required Action and associated Completion Time of Condition A not met.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Secondary Containment 3.6.4.1 CLINTON 3.6-44 Amendment No. 192 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment.

C.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.

In accordance with the Surveillance Frequency Control Program (continued)

SCIDs 3.6.4.2 CLINTON 3.6-47 Amendment No. 147 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)

LCO 3.6.4.2 Each SCID shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTES------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIDs.

(continued)

SCIDs 3.6.4.2 CLINTON 3.6-49 Amendment No. 147 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.

D.1

NOTE---------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

Immediately

SGT System 3.6.4.3 CLINTON 3.6-51 Amendment No. 187 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary or secondary containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.

A.1 Restore SGT subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

SGT System 3.6.4.3 CLINTON 3.6-52 Amendment No. 187 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the primary or secondary containment.

NOTE------------

LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR C.2 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

Immediately Immediately D.

Two SGT subsystems inoperable in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

D.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

SGT System 3.6.4.3 CLINTON 3.6-53 Amendment No. 201 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the primary or secondary containment.

E.1 Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes with heaters operating.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling bypass damper can be opened and the fan started.

In accordance with the Surveillance Frequency Control Program

Control Room Ventilation System 3.7.3 CLINTON 3.7-4 Amendment No. 9 5 3.7 PLANT SYSTEM 3.7.3 Control Room Ventilation System LCO 3.7.3 Two Control Room Ventilation subsystems shall be OPERABLE.

NOTE---------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Control Room Ventilation subsystem inoperable for reasons other than Condition C.

A.1 Restore Control Room Ventilation subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE 3.

B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.

C.1 Initiate action to implement mitigating actions.

AND C.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND C.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days (continued)

Control Room Ventilation System 3.7.3 CLINTON 3.7-5 Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and Associated Completion Time of Condition C not met in MODE 1, 2, or 3.

D.1 Be in MODE 3.

AND D.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours E. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.

NOTE-------------

LCO 3.0.3 is not applicable.

E.1 Place OPERABLE Control Room Ventilation subsystem in high radiation mode.

OR E.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND E.2.2 Suspend CORE ALTERATIONS.

Immediately Immediately Immediately F. Two Control Room Ventilation subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition C.

NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE 3.

F.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Control Room Ventilation System 3.7.3 CLINTON 3.7-6 Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two Control Room Ventilation subsystems inoperable during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.

OR One or more Control Room Ventilation subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.

G.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND G.2 Suspend CORE ALTERATIONS.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each Control Room Ventilation subsystem with flow through the makeup filter for 15 continuous minutes with the heaters operating.

In accordance with the Surveillance Frequency Control Program SR 3.7.3.2 Operate each Control Room Ventilation subsystem with flow through the recirculation filter for 15 minutes.

In accordance with the Surveillance Frequency Control Program (continued)

Control Room AC System 3.7.4 CLINTON 3.7-8 Amendment No. 9 5 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC subsystem inoperable.

A.1 Restore control room AC subsystem to OPERABLE status.

30 days B. Two control room AC subsystems inoperable.

B.1 Verify control room area temperature 86 ºF.

AND B.2 Restore one control room AC subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 7 days C. Required Action and Associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

NOTE------------

LCO 3.0.4.a is not applicable when entering MODE 3.

C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Control Room AC System 3.7.4 CLINTON 3.7-9 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.

NOTE-------------

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE control room AC subsystem in operation.

OR D.2.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND D.2.2 Suspend CORE ALTERATIONS.

Immediately Immediately Immediately (continued)

Control Room AC System 3.7.4 CLINTON 3.7-10 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition B not met during movement of irradiated fuel assemblies in the primary or secondary containment, or during CORE ALTERATIONS.

NOTE-------------

LCO 3.0.3 is not applicable.

E.1 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND E.2 Suspend CORE ALTERATIONS.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the capability to remove the assumed heat load.

In accordance with the Surveillance Frequency Control Program

AC Sources Shutdown 3.8.2 CLINTON 3.8-16 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown";

b.

One diesel generator (DG) capable of supplying one division of the Division 1 or 2 onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and

c.

One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission network and the Division 3 onsite Class 1E AC electrical power distribution subsystem, or the Division 3 DG capable of supplying the Division 3 onsite Class 1E AC electrical power distribution subsystem, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTE----------------------------------

LCO 3.0.3 is not applicable.

(continued)

AC Sources Shutdown 3.8.2 CLINTON 3.8-17 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO Item a not met.

NOTE-------------

Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.

A.1 Declare affected required feature(s) with no offsite power available from a required circuit inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND A.2.3 Initiate action to restore required offsite power circuit to OPERABLE status.

Immediately Immediately Immediately Immediately (continued)

AC Sources Shutdown 3.8.2 CLINTON 3.8-18 Amendment No. 95 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. LCO Item b not met.

B.1 Suspend CORE ALTERATIONS.

AND B.2 Suspend movement of irradiated fuel assemblies in primary and secondary containment.

AND B.3 Initiate action to restore required DG to OPERABLE status.

Immediately Immediately Immediately C. LCO Item c not met.

C.1 Declare High Pressure Core Spray System inoperable.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

DC Sources Shutdown 3.8.5 CLINTON 3.8-27 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 The following shall be OPERABLE:

a.

One Class 1E DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems -

Shutdown";

b.

One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or Division 2 onsite Class 1E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and

c.

The Division 3 and 4 DC electrical power subsystems capable of supplying the Division 3 and 4 onsite Class 1E DC electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

ACTIONS

NOTE-------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One battery charger on one division inoperable.

A.1 Restore battery terminal voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify battery float current < 2 amps.

AND A.3 Restore battery charger to OPERABLE status.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 7 days (continued)

DC Sources Shutdown 3.8.5 CLINTON 3.8-28 Amendment No. 142 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required DC electrical power subsystems inoperable for reasons other than Condition A.

OR Required Action and associated Completion Time of Condition A not met.

B.1 Declare affected required feature(s) inoperable.

OR B.2.1 Suspend CORE ALTERATIONS.

AND Immediately Immediately B.2.2 Suspend movement of irradiated fuel assemblies in the primary and secondary containment.

AND Immediately B.2.3 Initiate action to restore required DC electrical power subsystems to OPERABLE status.

Immediately

Inverters-Shutdown 3.8.8 CLINTON 3.8-36 Amendment No. XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters Shutdown LCO 3.8.8 The following Divisional inverters shall be OPERABLE:

a.

One Divisional inverter capable of supplying one division of the Division 1 or 2 onsite Class 1E uninterruptible AC bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b.

The Division 3 and 4 Divisional inverters capable of supplying the Division 3 and 4 onsite Class 1E uninterruptible AC bus electrical power distribution subsystems, when the High Pressure Core Spray System is OPERABLE for compliance with LCO 3.5.2, RPV Water Inventory Control.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the primary or secondary containment.

Inverters Shutdown 3.8.8 CLINTON 3.8-37 Amendment No. 95 ACTIONS

NOTE-------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required divisional inverters inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND Immediately Immediately A.2.2 Suspend handling of irradiated fuel assemblies in the primary and secondary containment.

AND Immediately A.2.3 Initiate action to restore required divisional inverters to OPERABLE status.

Immediately

Distribution Systems Shutdown 3.8.10 CLINTON 3.8-43 Amendment No. 192 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.3 Initiate actions to restore required AC, DC, and uninterruptible AC bus electrical power distribution subsystems to OPERABLE status.

AND A.2.4 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and uninterruptible AC bus electrical power distribution subsystems.

In accordance with the Surveillance Frequency Control Program

Clinton Power Station, Unit 1 Supplement to Clinton Power Station, Unit 1 Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" ATTACHMENT 4 TECHNICAL SPECIFICATIONS BASES PAGES AFFECTED BY THE ADDITIONAL VARIATION (MARK-UP)

B 3.3-122c B 3.3-122d B 3.3-122e B 3.3-122f B 3.3-122g B 3.3-122h B 3.3-122i B 3.5-26

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122c Revision No. 0 BASES APPLICABLE Low Pressure Core Spray and Low Pressure Coolant Injection SAFETY Systems ANALYSES, LCO, and APPLICABILITY 1.a, 2.a. Reactor Vessel Pressure - Low (Injection (continued)

Permissive)

Low reactor vessel pressure signals are used as permissives for the low pressure ECCS subsystems. This ensures that, prior to opening the injection valves of the low pressure ECCS subsystems, the reactor pressure has fallen to a value below these subsystems' maximum design pressure. While it is assured during Modes 4 and 5 that the reactor vessel pressure will be below the ECCS maximum design pressure, the Reactor vessel Pressure - Low signals are assumed to be operable and capable of permitting initiation of the ECCS.

The Reactor Vessel Pressure - Low signals are initiated from four pressure transmitters that sense the reactor dome pressure. The four pressure transmitters each drive ATMs (with a total of eight trip channels).

The Allowable Value is low enough to prevent overpressurizing the equipment in the low pressure ECCS.

Four channels of Reactor Vessel Pressure - Low Function per associated ECCS Division are required to be OPERABLE in MODES 4 and 5 when ECCS Manual Initiation is required to be OPERABLE, since these channels support the manual initiation Function. In addition, the channels are only required when the associated ECCS subsystem is required to be OPERABLE by LCO 3.5.2.

1.b, 1.c, 2.b. Low Pressure Coolant Injection and Low Pressure Core Spray Pump Discharge Flow - Low (Bypass)

The minimum flow instruments are provided to protect the associated low pressure ECCS pump from overheating when the pump is operating and the associated injection valve is not fully open. The minimum flow line valve is opened when low flow is sensed, and the valve is automatically closed when the flow rate is adequate to protect the pump.

One flow transmitter per ECCS pump is used to detect the associated subsystems' flow rates. The logic is arranged such that each transmitter causes its associated minimum flow valve to open. The logic will close the minimum flow valve once the closure setpoint is exceeded. The LPCI minimum flow valves are time delayed such that the valves will not open for 8 seconds after the ATMs detect low flow.

The time delay is provided to limit reactor vessel inventory loss during the startup of the Residual Heat Removal (RHR) shutdown cooling mode (for RHR A and RHR B).

(continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122d Revision No. 0 BASES APPLICABLE The Pump Discharge Flow - Low Allowable Values are high SAFETY enough to ensure that the pump flow rate is sufficient to ANALYSES, LCO, protect the pump, yet low enough to ensure that the closure and APPLICABILITY of the minimum flow valve is initiated to allow full flow (continued) into the core.

One channel of the Pump Discharge Flow - Low Function is required to be OPERABLE in MODES 4 and 5 when the associated LPCS or LPCI pump is required to be OPERABLE by LCO 3.5.2 to ensure the pumps are capable of injecting into the Reactor Pressure Vessel when manually initiated.

High Pressure Core Spray System 3.a. Reactor Core Isolation Cooling (RCIC) Storage Tank Level - Low Low level in the RCIC Storage Tank indicates the unavailability of an adequate supply of makeup water from this normal source. Normally the suction valves between HPCS and the RCIC Storage Tank are open and water for HPCS injection would be taken from the RCIC Storage Tank.

However, if the water level in the RCIC Storage Tank falls below a preselected level, first the suppression pool suction valve automatically opens, and then the RCIC Storage Tank suction valve automatically closes. This ensures that an adequate supply of makeup water is available to the HPCS pump. To prevent losing suction to the pump, the suction valves are interlocked so that the suppression pool suction valve must be open before the RCIC Storage Tank suction valve automatically closes.

RCIC Storage Tank Level - Low signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated ATM can cause the suppression pool suction valve to open and the RCIC Storage Tank suction valve to close.

The RCIC Storage Tank Level - Low Function Allowable Value is high enough to ensure adequate pump suction head while water is being taken from the RCIC Storage Tank.

Two channels of the RCIC Storage Tank Level - Low Function are only required to be OPERABLE when HPCS is required to be OPERABLE to fulfill the requirements of LCO 3.5.2, HPCS is aligned to the RCIC Storage Tank, and the RCIC Storage Tank water level is not within the limits of SR 3.5.2.3.

(continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122e Revision No. 0 BASES APPLICABLE 3.b, 3.c. HPCS Pump Discharge Pressure - High (Bypass) and SAFETY HPCS System Flow Rate - Low (Bypass)

ANALYSES, LCO, and APPLICABILITY The minimum flow instruments are provided to protect the (continued)

HPCS pump from overheating when the pump is operating and the associated injection valve is not fully open. The minimum flow line valve is opened when low flow and high pump discharge pressure are sensed, and the valve is automatically closed when the flow rate is adequate to protect the pump or the discharge pressure is low (indicating the HPCS pump is not operating).

One flow transmitter is used to detect the HPCS System's flow rate. The logic is arranged such that the transmitter causes the minimum flow valve to open, provided the HPCS pump discharge pressure, sensed by another transmitter, is high enough (indicating the pump is operating). The logic will close the minimum flow valve once the closure setpoint is exceeded. (The valve will also close upon HPCS pump discharge pressure decreasing below the setpoint.)

The HPCS System Flow Rate - Low and HPCS Pump Discharge Pressure - High Allowable Value is high enough to ensure that pump flow rate is sufficient to protect the pump, yet low enough to ensure that the closure of the minimum flow valve is initiated to allow full flow into the core.

The HPCS Pump Discharge Pressure - High Allowable Value is set high enough to ensure that the valve will not be open when the pump is not operating.

One channel of each Function is required to be OPERABLE when HPCS is required to be OPERABLE by LCO 3.5.2 in MODES 4 and 5.

(continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122f Revision No. 0 BASES APPLICABLE RHR System Isolation SAFETY ANALYSES, LCO, 4.a - Reactor Vessel Water Level - Low. Level 3 and APPLICABILITY (continued)

The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low, Level 3 Function is only required to be OPERABLE when automatic isolation of the associated RHR penetration flow path is credited in calculating DRAIN TIME.

Reactor Vessel Water Level - Low, Level 3 signals are initiated from four level transmitters (two per trip system) that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 3 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.

The Reactor Vessel Water Level - Low, Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low, Level 3 Allowable Value (LCO 3.3.1.1),

since the capability to cool the fuel may be threatened.

(continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122g Revision No. 0 BASES APPLICABLE Reactor Water Cleanup (RWCU) System Isolation SAFETY ANALYSES, LCO, 5.a - Reactor Vessel Water level - Low Low, Level 2 and APPLICABILITY (continued)

The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level - Low Low, Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration flow paths associated with the RWCU System.

Reactor Vessel Water Level - Low Low, Level 2 is initiated from two channels per trip system that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. While four channels (two channels per trip system) of the Reactor Vessel Water Level - Low, Level 2 Function are available, only two channels (all in the same trip system) are required to be OPERABLE.

The Reactor Vessel Water Level - Low Low, Level 2 Allowable Value was chosen to be the same as the ECCS Reactor Vessel Water Level - Low Low, Level 2 Allowable Value (LCO 3.3.5.1), since the capability to cool the fuel may be threatened.

The Reactor Vessel Water Level - Low Low, Level 2 Function is only required to be OPERABLE when automatic isolation of the associated penetration flow path is credited in calculating DRAIN TIME.

ACTIONS A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels.

Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits (continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122h Revision No. 0 BASES ACTIONS will not result in separate entry into the Condition.

(continued)

Section 1.3 also specifies that Required Actions continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory measures for separate inoperable Condition entry for each inoperable RPV Water Inventory Control instrumentation channel.

A.1 Required Action A.1 directs entry into the appropriate Condition referenced in Table 3.3.5.2-1. The applicable Condition referenced in the Table is Function dependent.

Each time a channel is discovered inoperable, Condition A is entered for that channel and provides for transfer to the appropriate subsequent Condition.

B.1 and B.2 RHR System Isolation, Reactor Vessel Water Level - Low Level 3, and Reactor Water Cleanup System, Reactor Vessel Water Level - Low Low, Level 2 functions are applicable when automatic isolation of the associated penetration flow path is credited in calculating Drain Time. If the instrumentation is inoperable, Required Action B.1 directs an immediate declaration that the associated penetration flow path(s) are incapable of automatic isolation. Required Action B.2 directs calculation of DRAIN TIME. The calculation cannot credit automatic isolation of the affected penetration flow paths.

C.1 Low reactor vessel pressure signals are used as permissives for the low pressure ECCS injection/spray subsystem manual initiation functions. If this permissive is inoperable, manual initiation of ECCS is prohibited. Therefore, the permissive must be placed in the trip condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. With the permissive in the trip condition, manual initiation may be performed. Prior to placing the permissive in the tripped condition, the operator can take manual control of the pump and the injection valve to inject water into the RPV.

The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is intended to allow the operator time to evaluate any discovered inoperabilities and to place the channel in trip.

(continued)

RPV Water Inventory Control Instrumentation B 3.3.5.2 CLINTON B 3.3-122i Revision No. 0 BASES ACTIONS D.1 and D.2 (continued)

Required Actions D.1 and D.2 are intended to ensure that appropriate actions are taken if multiple, inoperable channels within the same Function result in a loss of automatic suction swap for the HPCS system from the RCIC storage tank to the suppression pool. The HPCS system must be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or the HPCS pump suction must be aligned to the suppression pool, since, if aligned, the function is already performed.

The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is acceptable because it minimizes the risk of HPCS being needed without an adequate water source while allowing time for restoration or alignment of HPCS pump suction to the suppression pool.

E.1 If an LPCI or LPCS Discharge Flow - Low bypass function or HPCS System Discharge Pressure - High or Flow Rate - Low bypass function is inoperable, there is a risk that the associated ECCS pump could overheat when the pump is operating and the associated injection valve is not fully open. In this condition, the operator can take manual control of the pump and the injection valve to ensure the pump does not overheat. If a manual initiation function is inoperable, the ECCS subsystem pumps can be started manually and the valves can be opened manually, but this is not the preferred condition.

The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time was chosen to allow time for the operator to evaluate and repair any discovered inoperabilities. The Completion Time is appropriate given the ability to manually start the ECCS pumps and open the injection valves and to manually ensure the pump does not overheat.

F.1 With the Required Action and associated Completion Time of Conditions C, D, E, or F not met, the associated ECCS injection/spray subsystem may be incapable of performing the intended function, and must be declared inoperable immediately.

(continued)

ECCS-ShutdownRPV Water Inventory Control B 3.5.2 CLINTON B 3.5-26 Revision No. 17-1 BASES SURVEILLANCE SR 3.5.2.8SR 3.5.2.4 (continued)

REQUIREMENTS (continued) in the correct position. The required ECCS subsystem shall be capable of being manually operated. This Surveillance verifies that the required LCPI subsystem, LPCS System, or HPCS System (including the associated pump and valve(s)) can be manually operated to provide additional RPV Water Inventory, if needed, without delay.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

This SR is modified by a Note that excludes vessel injection/spray during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

REFERENCES

1.

Information Notice 84-81 "Inadvertent Reduction in Primary Coolant Inventory in Boiling Water Reactors During Shutdown and Startup," November 1984.

2.

Information Notice 86-74, "Reduction of Reactor Coolant Inventory Because of Misalignment of RHR Valves," August 1986.

3.

Generic Letter 92-04, "Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f)," August 1992.

4.

NRC Bulletin 93-03, "Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs,"

May 1993.

5.

Information Notice 94-52, "Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone 1,"

July 1994.

6.

General Electric Service Information Letter No. 388, "RHR Valve Misalignment During Shutdown Cooling Operation for BWR 3/4/5/6," February 1983.

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