RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements: Difference between revisions

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{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 Exelon Generation                                                 630 65 7 2000 Office RS-20-115                                                                                 10 CFR 50.90 November 18, 2020 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington , DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station , Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 Exelon Generation RS-20-115 November 18, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 630 65 7 2000 Office Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 10 CFR 50.90


==Subject:==
==Subject:==
Application to Revise Technical Specifications to Adopt TSTF-582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements"
Application to Revise Technical Specifications to Adopt TSTF-582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements"  


==References:==
==References:==
: 1. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force , "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582 , Revision 0, 'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020
: 1. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0, 'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020
: 2. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582 , Revision 0, 'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020
: 2. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0, 'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020  


November 18, 2020 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRG-approved Industry/Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," (Reference 1), and also incorporates the variation described in Reference 2. provides a description and assessment of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change. Attachment 3 provides TS Bases pages marked up to show the associated TS Bases changes and is provided for information only.
November 18, 2020 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRG-approved Industry/Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," (Reference 1 ), and also incorporates the variation described in Reference 2. provides a description and assessment of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change. Attachment 3 provides TS Bases pages marked up to show the associated TS Bases changes and is provided for information only.
The proposed change has been reviewed by the Plant Operations Review Committees at each station in accordance with the requirements of the EGC Quality Assurance Program.
The proposed change has been reviewed by the Plant Operations Review Committees at each station in accordance with the requirements of the EGC Quality Assurance Program.
EGC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLllP). Approval of the proposed amendment is requested within six months of completion of the NRC's acceptance review. Once approved, the amendment shall be implemented within 60 days.
EGC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLllP). Approval of the proposed amendment is requested within six months of completion of the NRC's acceptance review. Once approved, the amendment shall be implemented within 60 days.
In accordance with 10 CFR 50 .91, "Notice for public comment; State consultation,"
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.
paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 18th day of November 2020.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 18th day of November 2020.
Respectfully, Pa+/-tR ~
Respectfully, Pa+/-tR~
Patrick R. Simpson Sr. Manager Licensing Attachments:
Patrick R. Simpson Sr. Manager Licensing Attachments:
: 1. Description and Assessment
: 1. Description and Assessment
: 2. Markup of Proposed Technical Specifications Pages
: 2. Markup of Proposed Technical Specifications Pages
: 3. Markup of Proposed Technical Specifications Bases Pages (For Information Only)
: 3. Markup of Proposed Technical Specifications Bases Pages (For Information Only)  


November 18, 2020 U.S. Nuclear Regulatory Commission Page 3 cc:   NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station (Dan Tesar)
November 18, 2020 U.S. Nuclear Regulatory Commission Page 3 cc:
Illinois Emergency Management Agency - Division of Nuclear Safety
NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station (Dan Tesar)
Illinois Emergency Management Agency - Division of Nuclear Safety  


ATTACHMENT 1 Description and Assessment
==1.0 DESCRIPTION==
 
ATTACHMENT 1 Description and Assessment Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," which is an approved change to the Improved Standard Technical Specifications (ISTS), into Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, Technical Specifications (TS). The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions in TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The proposed changes also include the variation described in TSTF-583 and discussed in Reference 3.
==1.0     DESCRIPTION==


Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," which is an approved change to the Improved Standard Technical Specifications (ISTS), into Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station , Units 1 and 2, Technical Specifications (TS). The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions in TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The proposed changes also include the variation described in TSTF-583 and discussed in Reference 3.
==2.0 ASSESSMENT==
2.0     ASSESSMENT 2.1     Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a {{letter dated|date=August 13, 2020|text=letter dated August 13, 2020}} (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station , Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.
2.1 Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a {{letter dated|date=August 13, 2020|text=letter dated August 13, 2020}} (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1 ). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.
EGC verified that the required ECCS injection/spray subsystem can be aligned and the pump started using relatively simple evolutions involving the manipulation of a small number of components. These actions can be performed in a short time (less than the minimum Drain Time of 1 hour) from the control room following plant procedures.
EGC verified that the required ECCS injection/spray subsystem can be aligned and the pump started using relatively simple evolutions involving the manipulation of a small number of components. These actions can be performed in a short time (less than the minimum Drain Time of 1 hour) from the control room following plant procedures.
2.2     Variations 2.2.1   Proposed TS Changes to Adopt TSTF-583-T, "TSTF-582 Diesel Generator Variation" TSTF-582, "RPV WIC Enhancements," states:
2.2 Variations 2.2.1 Proposed TS Changes to Adopt TSTF-583-T, "TSTF-582 Diesel Generator Variation" TSTF-582, "RPV WIC Enhancements," states:
The ECCS injection/spray subsystem required to be operable by LCO 3.5.2 must be capable of being manually started as defense-in-depth against an unexpected draining event. The changes in TSTF-542 did not assume automatic actuation of the ECCS subsystem . TS 3.5.2, Required Action D.1 requires an additional method of water injection and that the required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. However, LCO 3.5.2 does not assume that the onsite electrical power source will start automatically on an ECCS or loss of power signal.
The ECCS injection/spray subsystem required to be operable by LCO 3.5.2 must be capable of being manually started as defense-in-depth against an unexpected draining event. The changes in TSTF-542 did not assume automatic actuation of the ECCS subsystem. TS 3.5.2, Required Action D.1 requires an additional method of water injection and that the required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. However, LCO 3.5.2 does not assume that the onsite electrical power source will start automatically on an ECCS or loss of power signal.
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ATTACHMENT 1 Description and Assessment LCO 3.8.2, "AC Sources - Shutdown ," requires one offsite circuit and one diesel generator to be operable in Modes 4 and 5. SR 3.8 .2.1 lists the TS 3.8.1, "AC Sources -
ATTACHMENT 1 Description and Assessment LCO 3.8.2, "AC Sources - Shutdown," requires one offsite circuit and one diesel generator to be operable in Modes 4 and 5. SR 3.8.2.1 lists the TS 3.8.1, "AC Sources -
Operating," SRs that are applicable in Modes 4 and 5. In an oversight in TSTF-542 , the TS 3.8 .1 SRs that test automatic start and loading of a diesel generator on an ECCS or loss of offsite power signal were not excluded from SR 3.8.2 .1.
Operating," SRs that are applicable in Modes 4 and 5. In an oversight in TSTF-542, the TS 3.8.1 SRs that test automatic start and loading of a diesel generator on an ECCS or loss of offsite power signal were not excluded from SR 3.8.2.1.
TSTF-582 revises Technical Specification (TS) 3.8.2, "AC Sources - Shutdown," Surveillance Requirement (SR) 3.8.2 .1, to exclude SRs that verify the ability of the diesel generators to automatically start and load on an ECCS initiation signal or loss of offsite power signal.
TSTF-582 revises Technical Specification (TS) 3.8.2, "AC Sources - Shutdown," Surveillance Requirement (SR) 3.8.2.1, to exclude SRs that verify the ability of the diesel generators to automatically start and load on an ECCS initiation signal or loss of offsite power signal.
The NRC Safety Evaluation for TSTF-582 (ADAMS Accession No. ML20223AOOO, dated, August 13, 2020), Section 3.6, "Alternating Current Sources - Shutdown, STS 3.8.2," states:
The NRC Safety Evaluation for TSTF-582 (ADAMS Accession No. ML20223AOOO, dated, August 13, 2020), Section 3.6, "Alternating Current Sources - Shutdown, STS 3.8.2," states:
STS 3.5.2, "Reactor Pressure Vessel Water Inventory Control (RPV WIC)," does not require automatic ECCS initiation to mitigate a draining event in Modes 4 and 5, and the ECCS initiation signal related to the automatic ECCS initiation is removed from the STS .
STS 3.5.2, "Reactor Pressure Vessel Water Inventory Control (RPV WIC)," does not require automatic ECCS initiation to mitigate a draining event in Modes 4 and 5, and the ECCS initiation signal related to the automatic ECCS initiation is removed from the STS.
Because the automatic ECCS initiation and related ECCS initial signal in Modes 4 and 5 are eliminated , the automatic start of the DG on an ECCS initiation signal is not required in Modes 4 and 5 . ... [T]he NRC staff finds that STS 3.5.2 provides enough time from the onset of the [loss of offsite power] LOOP event for the operator to manually start the DG required to supply power to the water injection equipment to mitigate the draining event in Modes 4 and 5. In addition, STS 3.5.2 does not require the automatic initiation of the ECCS injection/spray subsystem or the additional method of water injection . Therefore, since STS 3.5.2 allows enough time to manually start the DG and the equipment for water injection, the NRC staff finds that the automatic start and loading of the DG are not necessary on a LOOP signal or LOOP concurrent with an ECCS initiation signal to mitigate a draining event in Modes 4 and 5.
Because the automatic ECCS initiation and related ECCS initial signal in Modes 4 and 5 are eliminated, the automatic start of the DG on an ECCS initiation signal is not required in Modes 4 and 5.... [T]he NRC staff finds that STS 3.5.2 provides enough time from the onset of the [loss of offsite power] LOOP event for the operator to manually start the DG required to supply power to the water injection equipment to mitigate the draining event in Modes 4 and 5. In addition, STS 3.5.2 does not require the automatic initiation of the ECCS injection/spray subsystem or the additional method of water injection. Therefore, since STS 3.5.2 allows enough time to manually start the DG and the equipment for water injection, the NRC staff finds that the automatic start and loading of the DG are not necessary on a LOOP signal or LOOP concurrent with an ECCS initiation signal to mitigate a draining event in Modes 4 and 5.
Furthermore, the NRC staff notes that other events postulated in Modes 4 and 5 (e.g. ,
Furthermore, the NRC staff notes that other events postulated in Modes 4 and 5 (e.g.,
FHA, waste gas tank rupture) and during movement of [recently] irradiated fuel assemblies in the [primary and secondary containment] do not assume a LOOP event or an automatic ECCS initiation .
FHA, waste gas tank rupture) and during movement of [recently] irradiated fuel assemblies in the [primary and secondary containment] do not assume a LOOP event or an automatic ECCS initiation.
TSTF-582 did not include all of the TS changes needed to reflect that TS 3.8.2 should not require automatic start and loading of a diesel generator within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities) on an ECCS initiation signal or a loss of offsite power signal.
TSTF-582 did not include all of the TS changes needed to reflect that TS 3.8.2 should not require automatic start and loading of a diesel generator within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities) on an ECCS initiation signal or a loss of offsite power signal.
* TS 3.3.8.1 , "Loss of Power (LOP) Instrumentation," is applicable in Modes 1, 2, and 3, and when the associated diesel generator is required to be operable by TS 3.8.2. TSTF-582 revised TS 3.8.2 to no longer require automatic start and loading of a diesel generator on a loss of offsite power signal. Consequently, the LOP instrumentation that generates the loss of offsite power signal should not be required to be operable when the diesel generator is required to be operable by TS 3.8.2. The Applicability of LCO 3.3.8.1 is revised to not include the specified condition "When the associated diesel generator is required to be OPERABLE by LCO 3.8.2 , 'AC Sources - Shutdown'."
TS 3.3.8.1, "Loss of Power (LOP) Instrumentation," is applicable in Modes 1, 2, and 3, and when the associated diesel generator is required to be operable by TS 3.8.2. TSTF-582 revised TS 3.8.2 to no longer require automatic start and loading of a diesel generator on a loss of offsite power signal. Consequently, the LOP instrumentation that generates the loss of offsite power signal should not be required to be operable when the diesel generator is required to be operable by TS 3.8.2. The Applicability of LCO 3.3.8.1 is revised to not include the specified condition "When the associated diesel generator is required to be OPERABLE by LCO 3.8.2, 'AC Sources - Shutdown'."
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ATTACHMENT 1 Description and Assessment
ATTACHMENT 1 Description and Assessment TS SR 3.8.1.7 and SR 3.8.1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), require that the DG starts from standby or hot conditions, respectively, and achieve required voltage and frequency within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities). The 12 to 13 second start requirement supports the assumptions in the design basis LOCA analysis.
* TS SR 3.8.1.7 and SR 3.8 .1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1 .16 (for Dresden and Quad Cities), require that the DG starts from standby or hot conditions, respectively, and achieve required voltage and frequency within 12 to 13 seconds (12 seconds for Clinton , and 13 seconds for Dresden, LaSalle, and Quad Cities). The 12 to 13 second start requirement supports the assumptions in the design basis LOCA analysis.
This capability is not required during a manual diesel generator start to respond to a draining event, which has a minimum Drain Time of one hour. Therefore, SR 3.8.1.7 and SR 3.8.1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), are added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.
This capability is not required during a manual diesel generator start to respond to a draining event, which has a minimum Drain Time of one hour. Therefore, SR 3.8.1.7 and SR 3.8.1 .15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), are added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.
These SRs are not included under SR 3.8.2.1.
These SRs are not included under SR 3.8.2.1.
* Clinton, Dresden, and Quad Cities TS SR 3.8.1.18 state "Verify interval between each sequenced load block is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed . The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1
Clinton, Dresden, and Quad Cities TS SR 3.8.1.18 state "Verify interval between each sequenced load block is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed. The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1 LaSalle TS SR 3.8.1.18 state "Verify interval between each sequenced load block, for Division 1 and 2 DGs only, is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed. The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1 The TS 3.8.2 LCO Bases were not updated by TSTF-542 or TSTF-582 to reflect that automatic start and loading of a diesel generator is not required. The LCO 3.8.2 and SR 3.8.2.1 Bases are revised to reflect the TS requirements.
* LaSalle TS SR 3.8 .1 .18 state "Verify interval between each sequenced load block, for Division 1 and 2 DGs only, is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed . The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1 . This SR is not included under SR 3.8 .2.1 The TS 3.8.2 LCO Bases were not updated by TSTF-542 or TSTF-582 to reflect that automatic start and loading of a diesel generator is not required. The LCO 3.8.2 and SR 3.8.2.1 Bases are revised to reflect the TS requirements .
This variation provides consistency within the TS after incorporating the TSTF-582 changes to SR 3.8.2.1.
This variation provides consistency within the TS after incorporating the TSTF-582 changes to SR 3.8.2 .1.
As an editorial improvement, SR 3.8.2.1 is revised to list the TS 3.8.1 SRs that are applicable instead of listing the TS 3.8.1 SRs that are not applicable. The SR 3.8.2.1 Bases are not affected and explain why the omitted TS 3.8.1 SRs are not applicable to TS 3.8.2.
As an editorial improvement, SR 3.8.2.1 is revised to list the TS 3.8.1 SRs that are applicable instead of listing the TS 3.8 .1 SRs that are not applicable. The SR 3.8.2.1 Bases are not affected and explain why the omitted TS 3.8.1 SRs are not applicable to TS 3.8.2.
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ATTACHMENT 1 Description and Assessment 2.2.2  Editorial Variations The Clinton, Dresden, LaSalle, and Quad Cities TS utilize different numbering and titles than the Standard Technical Specifications on which TSTF-582 and TSTF-583-T were based . Table 1 describes the differences between the plant-specific TS numbering and titles and the TSTF-582 and TSTF-583T numbering and titles. These differences are administrative and do not affect the applicability of TSTF-582 to these plant's TS.
Table 1. TSTF-582 and TSTF-583-T BWR4 and BWRG Numbering and Title Variations TSTF-582 (BWR4)                      Dresden                      Quad Cities Table 3.3.5.2-1                  Table 3.3.5.2 System      Table 3.3.5.2 System
  - RHR System Isolation          nomenclature difference      nomenclature difference
                                  - Shutdown Cooling            - RHR Shutdown Cooling System (SOC) Isolation        System (SOC) Isolation SR 3.5.2 .5                      Numbering difference          Numbering difference
                                  - SR 3.5.2.4                  - SR 3.5.2.4 -
SR 3.5.2.7                      Numbering difference          Numbering difference
                                  - SR 3.5.2 .6 -              - SR 3.5.2.6 TS 3.6 .1.3 Condition F          Numbering difference          Numbering difference
                                  - TS 3.6.1.3 Condition E -    - TS 3.6.1 .3 Condition E TSTF-583-T (BWR4)                      Dresden                      Quad Cities SR 3.8.1.9                      Numbering difference          Numbering difference
                                  -  SR3.8.1.10                -  SR 3.8.1.10 SR3.8.1.10                      Numbering difference          Numbering difference
                                  -  SR 3.8.1.11                -  SR 3.8.1.11 SR3.8.1.14                      Numbering difference          Numbering difference
                                  -  SR3.8.1.15                -  SR 3.8.1.15 SR3.8.1.16                      Numbering difference          Numbering difference
                                  -  SR3.8.1.17                -  SR 3.8.1.17 TSTF-582 (BWR6)                        Clinton                      LaSalle Table 3.3.5.2-1                  N/A                          System nomenclature RHR System Isolation                                          difference
                                                                - RHR Shutdown Cooling System Isolation TS 3.3 .6.1 Required Action      Numbering difference          N/A J.2                              -  TS 3.3.6.1 Required Action M.2 Page4


ATTACHMENT 1 Description and Assessment 2.2.3  Other Variations 2.2.3.1 Clinton, Dresden, LaSalle, and Quad Cities Additional Variations EGC is proposing the following additional variations from the TS changes described in TSTF-582. The variations are described in Table 2. These variations do not affect the applicability of TSTF-582 to the proposed license amendments.
2.2.2 Editorial Variations ATTACHMENT 1 Description and Assessment The Clinton, Dresden, LaSalle, and Quad Cities TS utilize different numbering and titles than the Standard Technical Specifications on which TSTF-582 and TSTF-583-T were based. Table 1 describes the differences between the plant-specific TS numbering and titles and the TSTF-582 and TSTF-583T numbering and titles. These differences are administrative and do not affect the applicability of TSTF-582 to these plant's TS.
Table 2. TSTF-582 BWR4 and BWRG Other Variations TSTF-582 (BWR4)                   Dresden             Quad Cities           Comments SR 3.3.5.2.3                    No equivalent SR        No equivalent SR      No changes made TS 3.6 .1.3 Condition G          No equivalent          No equivalent        No changes made condition              condition TS 3.6 .1.3 Condition H          No equivalent          No equivalent        No changes made condition              condition TSTF-582 (BWR6)                   Clinton                LaSalle            Comments TS 3.3 .5.2 Conditions D        No equivalent          No equivalent        No changes made and E                            Condition E            Conditions D and E SR 3.3.5 .2.3                    No equivalent SR        No equivalent SR      No changes made SR 3.5.2.7                       No equivalent SR       N/A                  No changes made 2.2.3.2 Clinton Specific Variation EGC is proposing the following variations from the TS changes described in TSTF-582 for Clinton Power Station. EGC is proposing to delete TS 3.3 .6.1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 . These are not included in TSTF-582. With the TSTF-582 deletion of TS 3.3.6.1 M.2 for Clinton (J.2 in TSTF-582), TS 3.3.6. 1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 are no longer applicable. These Clinton specific actions are no longer applicable after adoption of TSTF-542 (Reference 5, 6, and 7). Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 should be deleted with the deletion of TS 3.3.6.1 M.2. This plant specific variation does not impact the applicability of TSTF-582 to the Clinton TS.
Table 1. TSTF-582 and TSTF-583-T BWR4 and BWRG Numbering and Title Variations TSTF-582 (BWR4)
Page 5
Dresden Quad Cities Table 3.3.5.2-1 Table 3.3.5.2 System Table 3.3.5.2 System RHR System Isolation nomenclature difference nomenclature difference Shutdown Cooling RHR Shutdown Cooling System (SOC) Isolation System (SOC) Isolation SR 3.5.2.5 Numbering difference Numbering difference SR 3.5.2.4 SR 3.5.2.4 -
SR 3.5.2.7 Numbering difference Numbering difference SR 3.5.2.6 -
SR 3.5.2.6 TS 3.6.1.3 Condition F Numbering difference Numbering difference TS 3.6.1.3 Condition E -
TS 3.6.1.3 Condition E TSTF-583-T (BWR4)
Dresden Quad Cities SR 3.8.1.9 Numbering difference Numbering difference SR3.8.1.10 SR 3.8.1.10 SR3.8.1.10 Numbering difference Numbering difference SR 3.8.1.11 SR 3.8.1.11 SR3.8.1.14 Numbering difference Numbering difference SR3.8.1.15 SR 3.8.1.15 SR3.8.1.16 Numbering difference Numbering difference SR3.8.1.17 SR 3.8.1.17 TSTF-582 (BWR6)
Clinton LaSalle Table 3.3.5.2-1 N/A System nomenclature RHR System Isolation difference RHR Shutdown Cooling System Isolation TS 3.3.6.1 Required Action Numbering difference N/A J.2 TS 3.3.6.1 Required Action M.2 Page4


ATTACHMENT 1 Description and Assessment
2.2.3 Other Variations ATTACHMENT 1 Description and Assessment 2.2.3.1 Clinton, Dresden, LaSalle, and Quad Cities Additional Variations EGC is proposing the following additional variations from the TS changes described in TSTF-582. The variations are described in Table 2. These variations do not affect the applicability of TSTF-582 to the proposed license amendments.
Table 2. TSTF-582 BWR4 and BWRG Other Variations TSTF-582 (BWR4)
Dresden Quad Cities Comments SR 3.3.5.2.3 No equivalent SR No equivalent SR No changes made TS 3.6.1.3 Condition G No equivalent No equivalent No changes made condition condition TS 3.6.1.3 Condition H No equivalent No equivalent No changes made condition condition TSTF-582 (BWR6)
Clinton LaSalle Comments TS 3.3.5.2 Conditions D No equivalent No equivalent No changes made and E Condition E Conditions D and E SR 3.3.5.2.3 No equivalent SR No equivalent SR No changes made SR 3.5.2.7 No equivalent SR N/A No changes made 2.2.3.2 Clinton Specific Variation EGC is proposing the following variations from the TS changes described in TSTF-582 for Clinton Power Station. EGC is proposing to delete TS 3.3.6.1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4. These are not included in TSTF-582. With the TSTF-582 deletion of TS 3.3.6.1 M.2 for Clinton (J.2 in TSTF-582), TS 3.3.6. 1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 are no longer applicable. These Clinton specific actions are no longer applicable after adoption of TSTF-542 (Reference 5, 6, and 7). Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 should be deleted with the deletion of TS 3.3.6.1 M.2. This plant specific variation does not impact the applicability of TSTF-582 to the Clinton TS.
Page 5


==3.0    REGULATORY ANALYSIS==
ATTACHMENT 1 Description and Assessment


3.1     No Significant Hazards Consideration Determination Analysis Exelon Generation Company, LLC (EGC), requests adoption of TSTF 582 , "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements." The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions that were incorporated into the plant TS when adopting TSTF-542 , Revision 2, "Reactor Pressure Vessel Water Inventory Control." TSTF-582 includes the following changes to the TS:
==3.0 REGULATORY ANALYSIS==
: 1. The Drain Time definition is revised to move the examples of common mode failure mechanisms to the Bases and seismic events are no longer considered a common mode failure mechanism .
3.1 No Significant Hazards Consideration Determination Analysis Exelon Generation Company, LLC (EGC), requests adoption of TSTF 582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements." The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." TSTF-582 includes the following changes to the TS:
: 1. The Drain Time definition is revised to move the examples of common mode failure mechanisms to the Bases and seismic events are no longer considered a common mode failure mechanism.
: 2. The Drain Time definition exception from considering the Drain Time for penetration flow paths isolated with manual or automatic valves that are "locked, sealed, or otherwise secured" is revised to apply the exception for manual or automatic valves that are "closed and administratively controlled."
: 2. The Drain Time definition exception from considering the Drain Time for penetration flow paths isolated with manual or automatic valves that are "locked, sealed, or otherwise secured" is revised to apply the exception for manual or automatic valves that are "closed and administratively controlled."
: 3. The TS are revised to permit placing an inoperable isolation channel in trip as an alternative to declaring the associated penetration flow path incapable of automatic isolation .
: 3. The TS are revised to permit placing an inoperable isolation channel in trip as an alternative to declaring the associated penetration flow path incapable of automatic isolation.
: 4. A Surveillance Requirement (SR) that requires operating the required Emergency Core Cooling System (ECCS) injection/spray subsystem for at least 10 minutes through the recirculation line , is modified to permit crediting normal operation of the system to satisfy the SR and to permit operation through the test return line.
: 4. A Surveillance Requirement (SR) that requires operating the required Emergency Core Cooling System (ECCS) injection/spray subsystem for at least 10 minutes through the recirculation line, is modified to permit crediting normal operation of the system to satisfy the SR and to permit operation through the test return line.
: 5. Dresden, Unit 2 and 3 share secondary containment structures between units. LaSalle, Unit 1 and 2 share secondary containment structures between units. Quad Cities, Unit 1 and 2 share secondary containment structures between units. The TS Actions are revised to recognize that an operable secondary containment and operable secondary containment isolation valves satisfy the Required Actions.
: 5. Dresden, Unit 2 and 3 share secondary containment structures between units. LaSalle, Unit 1 and 2 share secondary containment structures between units. Quad Cities, Unit 1 and 2 share secondary containment structures between units. The TS Actions are revised to recognize that an operable secondary containment and operable secondary containment isolation valves satisfy the Required Actions.
: 6. The Clinton, Dresden, LaSalle , and Quad Cities designs contain additional isolation instrumentation functions based on low RPV water level that could be credited when calculating Drain Time. Those functions are added to the required functions in TS 3.3.5 .2.
: 6. The Clinton, Dresden, LaSalle, and Quad Cities designs contain additional isolation instrumentation functions based on low RPV water level that could be credited when calculating Drain Time. Those functions are added to the required functions in TS 3.3.5.2.
: 7. TS 3.8.2, "AC Sources - Shutdown ," SR 3.8 .2.1, is revised to not require SRs that test the ability of the automatic diesel generator to start in Modes 4 and 5. Automatic ECCS Page 6
: 7. TS 3.8.2, "AC Sources - Shutdown," SR 3.8.2.1, is revised to not require SRs that test the ability of the automatic diesel generator to start in Modes 4 and 5. Automatic ECCS Page 6  


ATTACHMENT 1 Description and Assessment initiation in Modes 4 and 5 was eliminated in TSTF-542. This was an oversight in TSTF-542.
ATTACHMENT 1 Description and Assessment initiation in Modes 4 and 5 was eliminated in TSTF-542. This was an oversight in TSTF-542.
: 8. TS 3.3 .6.1, "Primary Containment Isolation Instrumentation," Required Action J.2 (J .2 for LaSalle and M.2 for Clinton) is deleted . This action is no longer applicable after adoption of TSTF-542. This was an accidental omission in TSTF-542. This change is made for clarity and has no effect on the application of the TS .
: 8. TS 3.3.6.1, "Primary Containment Isolation Instrumentation," Required Action J.2 (J.2 for LaSalle and M.2 for Clinton) is deleted. This action is no longer applicable after adoption of TSTF-542. This was an accidental omission in TSTF-542. This change is made for clarity and has no effect on the application of the TS.
: 9. The Applicability of TS 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," is revised to delete the phrase, "When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, 'Primary Containment Isolation Instrumentation'." This makes TS 3.6.1.3 only applicable Modes 1, 2, and 3. Following adoption of TSTF-542, no functions in LCO 3.3.6 .1 are applicable outside of Modes 1, 2, or 3. The Actions and SRs are revised to reflect this change. These changes are made for clarity and have no effect on the application of the TS.
: 9. The Applicability of TS 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," is revised to delete the phrase, "When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, 'Primary Containment Isolation Instrumentation'." This makes TS 3.6.1.3 only applicable Modes 1, 2, and 3. Following adoption of TSTF-542, no functions in LCO 3.3.6.1 are applicable outside of Modes 1, 2, or 3. The Actions and SRs are revised to reflect this change. These changes are made for clarity and have no effect on the application of the TS.
: 10. The TS are revised to use wording and to define acronyms in a manner consistent with the remainder of the TS. These changes are made for consistency and have no effect on the application of the TS.
: 10. The TS are revised to use wording and to define acronyms in a manner consistent with the remainder of the TS. These changes are made for consistency and have no effect on the application of the TS.
EGC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
EGC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
: 1.     Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
: 1.
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." Draining of RPV water inventory in Mode 4 (i.e., cold shutdown) and Mode 5 (i.e., refueling) is not an accident previously evaluated and , therefore , revising the existing TS controls to prevent or mitigate such an event has no effect on any accident previously evaluated. RPV water inventory control in Mode 4 or Mode 5 is not an initiator of any accident previously evaluated. The existing and revised TS controls are not mitigating actions assumed in any accident previously evaluated .
Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated .
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." Draining of RPV water inventory in Mode 4 (i.e., cold shutdown) and Mode 5 (i.e., refueling) is not an accident previously evaluated and, therefore, revising the existing TS controls to prevent or mitigate such an event has no effect on any accident previously evaluated. RPV water inventory control in Mode 4 or Mode 5 is not an initiator of any accident previously evaluated. The existing and revised TS controls are not mitigating actions assumed in any accident previously evaluated.
Page 7
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Page 7  


ATTACHMENT 1 Description and Assessment
ATTACHMENT 1 Description and Assessment
: 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
: 2.
Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The event of concern under the current requirements and the proposed change is an unexpected draining event. The TS have contained requirements related to an unexpected draining event during shutdown for over 40 years and this event does not appear as an analyzed event in the Updated Final Safety Analysis Report (UFSAR) for any plant or in the NRC's Standard Review Plan (NUREG- 0800). Therefore, an unexpected draining event is not a new or different kind of accident not considered in the design and licensing bases that would have been considered a design basis accident in the UFSAR had it been previously identified.
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The event of concern under the current requirements and the proposed change is an unexpected draining event. The TS have contained requirements related to an unexpected draining event during shutdown for over 40 years and this event does not appear as an analyzed event in the Updated Final Safety Analysis Report (UFSAR) for any plant or in the NRC's Standard Review Plan (NUREG- 0800). Therefore, an unexpected draining event is not a new or different kind of accident not considered in the design and licensing bases that would have been considered a design basis accident in the UFSAR had it been previously identified.
None of the equipment affected by the proposed change has a design function described in the UFSAR to mitigate an unexpected draining event in Modes 4 or 5, although the equipment may be used for that purpose. Therefore, the proposed amendment will not change the design function of the affected equipment. The proposed change will affect the operation of certain equipment, such as the manual initiation function and related instrumentation to permit initiation of the required ECCS injection/spray subsystem, and the control of valves credited for preventing a draining event. However, these changes provide adequate protection to prevent or mitigate an unexpected draining event and do not create the possibility of a new or different kind of accident due to credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.
None of the equipment affected by the proposed change has a design function described in the UFSAR to mitigate an unexpected draining event in Modes 4 or 5, although the equipment may be used for that purpose. Therefore, the proposed amendment will not change the design function of the affected equipment. The proposed change will affect the operation of certain equipment, such as the manual initiation function and related instrumentation to permit initiation of the required ECCS injection/spray subsystem, and the control of valves credited for preventing a draining event. However, these changes provide adequate protection to prevent or mitigate an unexpected draining event and do not create the possibility of a new or different kind of accident due to credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
: 3. Does the proposed change involve a significant reduction in a margin of safety?
: 3.
Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The safety basis for the RPV WIC requirements is to protect Safety Limit 2.1.1.3. The proposed change does not affect any specific values that define a safety margin as established in the licensing basis. The proposed change does not affect a design basis or safety limit, or any controlling value for a parameter established in the UFSAR or the license.
Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The safety basis for the RPV WIC requirements is to protect Safety Limit 2.1.1.3. The proposed change does not affect any specific values that define a safety margin as established in the licensing basis. The proposed change does not affect a design basis or safety limit, or any controlling value for a parameter established in the UFSAR or the license.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Page 8
Page 8  
 
ATTACHMENT 1 Description and Assessment Based on the above, EGC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50 .92(c), and , accordingly, a finding of "no significant hazards consideration" is justified.
3.2    Conclusions In conclusion , based on the considerations discussed above , (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.


==4.0    ENVIRONMENTAL CONSIDERATION==
ATTACHMENT 1 Description and Assessment Based on the above, EGC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
3.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.  


==4.0 ENVIRONMENTAL CONSIDERATION==
The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.  


==5.0     REFERENCES==
==5.0 REFERENCES==
: 1. Letter from the Technical Specifications Task Force to the U.S. Nuclear Regulatory Commission , "Transmittal of TSTF-582, Revision 0, RPV WIC Enhancements,"' dated August28 , 2019
: 1. Letter from the Technical Specifications Task Force to the U.S. Nuclear Regulatory Commission, "Transmittal of TSTF-582, Revision 0, RPV WIC Enhancements,"' dated August28, 2019
: 2. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,
: 2. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,  
    'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020
'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020
: 3. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,
: 3. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,  
    'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process, " dated October 9, 2020
'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020
: 4. NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 4, dated April 2012 Page 9
: 4. NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 4, dated April 2012 Page 9  


ATTACHMENT 1 Description and Assessment
ATTACHMENT 1 Description and Assessment
: 5. NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants, Volume 1, Revision 4, dated April 2012
: 5. NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants, Volume 1, Revision 4, dated April 2012
: 6. Letter from Alexander R. Klein (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ," dated December 20, 2016
: 6. Letter from Alexander R. Klein (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control," dated December 20, 2016
: 7. Letter from P. Simpson (EGC) to U.S. NRC, "Application to Revise Technical Specifications Following Adoption of TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,"' dated June 18, 2019 Page 10
: 7. Letter from P. Simpson (EGC) to U.S. NRC, "Application to Revise Technical Specifications Following Adoption of TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,"' dated June 18, 2019 Page 10  


ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 1.0-3 1.0-4 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-51 3.3-52 3.3-78 3.8-19
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 1.0-3 1.0-4 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-51 3.3-52 3.3-78 3.8-19  


Definitions 1.1 1.1 Definitions   (continued)
Definitions 1.1 1.1 Definitions (continued)
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 re l oad cycle in accordance with Specification 5 . 6 . 5 .     Plant operation within these limits is addressed in individual Specifications .
CORE OPERATING LIMITS REPORT (COLR)
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 ,
DOSE EQUIVALENT I - 131 DRAIN TIME CLINTON The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.
I - 133 , I - 134 , and I - 135 actually present . The inhalation CE DE 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 ,
These cycle specific limits shall be determined for each re l oad cycle in accordance with Specification 5. 6. 5.
Plant operation within these limits is addressed in individual Specifications.
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.
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 :
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 I 8ei8mic e u ent , .l.B-8-& M normal po 1er , Bingle R-Yma-n error ) , for all 1
The water inventory above the TAF is divided by the limiting drain rate;
(co nt inued)
: b.
CLINTON                                    1.0 - 3                     Amendment No.     ~
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 I
8ei8mic e uent,.l.B-8-& M normal po 1 1er, Bingle R-Yma-n error ), for all (continued) 1.0- 3 Amendment No. ~  


Definitions
Definitions DRAIN TIME (continued)
: 1. 1 closed and administratively controlled Definitions DRA IN TIME                  penetrat i on flow paths below the TAF except (continued )
EMERGENCY CORE COOLING SYSTEM (ECCS ) RESPONSE TIME CLINTON Definitions
: 1. Penetration flow paths connected to an int a ct closed system , or isolated by manual or automatic va l ves that are l ocked , sea l ed , G-t- otheri1ise secured in the closed position , b l ank flanges , or other devices that prevent flow of reactor coolant through the penetration flow paths ;
: 1. 1 closed and administratively controlled penetrati on flow paths below the TAF except 1.
: 2. Penetration flow paths capable of being isolated by va l ves that will c l ose automatical l y without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water l evel isolation instrumentat i on ; or
Penetration flow paths connected to an intact closed system, or isolated by manual or automatic va l ves that are l ocked, sea l ed,
: 3. Penetration flow paths with iso l ation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task ,
G-t-otheri1ise secured in the closed position, b l ank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths ;
who is in continuous communication with t h e control room, is stationed at the controls , and is capab l e of closing the penetration flow path i solation devices without offs i te power .
2.
: c. The penetration f l ow 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 ;
Penetration flow paths capable of being isolated by va l ves that will c l ose automatical l y without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water l evel isolation instrumentati on ; or 3.
: d. No addit i onal draining events occur ; and
Penetration flow paths with iso l ation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task,
: e. Realistic cross - sectional areas and drain rates are used .
who is in continuous communication with t h e control room, is stationed at the controls, and is capab l e of closing the penetration flow path i solation devices without offs i te power.
A bounding DRAIN TIME may be used in l ieu of a ca l culated va l ue .
: c.
EMERGENCY CORE COOLING  The ECCS RESPONSE TIME shall be that time i nterval SYSTEM (ECCS ) RESPONSE from when the monitored parameter exceeds its ECCS TIME                    initiation setpoint at the channel sensor until t h e ECCS equipment is capable of performing its safety function (i . e ., the valves travel to t h eir 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 meas u red by means of any ser i es of sequential ,
The penetration f l ow 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 ;
over l app i ng , or total steps so t h at the entire response time is measured .
d.
(co n tinued )
No addit i onal draining events occur ; and e.
CLINTON                            1.0 - 4                       Amendment No.   ~
Realistic cross - sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in l ieu of a ca l culated va l ue.
The ECCS RESPONSE TIME shall be that time i nterval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until t he ECCS equipment is capable of performing its safety function (i. e., the valves travel to t heir 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 seri es of sequential,
over l app i ng, or total steps so t hat the entire response time is measured.
(continued )
1.0- 4 Amendment No. ~  


RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 3.3        INSTRUMENTATION 3.3.5.2                   Reactor Pressure Vesse l     (RPV ) Water I nventory Control I nstrumentation LCO       3.3.5.2               The RPV Water I nventory Control instrumentation for each Function in Table 3 . 3 . 5 . 2 - 1 shall be OPERABLE .
3. 3 INSTRUMENTATION RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 3. 3. 5. 2 Reactor Pressure Vesse l (RPV ) Water I nventory Control I nstrumentation LCO 3. 3. 5. 2 The RPV Water I nventory Control instrumentation for each Function in Table 3. 3. 5. 2-1 shall be OPERABLE.
APPLICABIL I TY :               According to Tab l e 3 . 3 . 5 . 2 - 1 .
APPLICABIL I TY :
ACTIONS
According to Tab l e 3. 3. 5. 2-1.
      ------------------------------------- NOTE -------------------------------------
ACTIONS  
Separate Condition entry is al l owed for each channel .
-------------------------------------NOTE-------------------------------------
CONDITION                       REQUIRED ACTION                  COMPLETION TIME A...- Gf+/-l. .g..:r. ~ QAClAA9la             ~          .t.f+/-. C9A9iti9A iA9j;;>Q:f ClQl9                       :fQfQ:fQAQQg .i-1:+
Separate Condition entry is al l owed for each channel.
                                                      ~ J J 5 2 f.G-:r-
CONDITION A...-
                                                      -t-M QAilAAQl AA   :r g qyi:r g g b¥-               Initiate action to              Immediately ggqyi:rgg Ai;;ti9A                       place channel in trip .
Gf+/-l..g..:r. ~
              .a.A4 :rgfg:r9AQ9G .i-1:+
QAClAA9la iA9j;;>Q:f ClQl9 One or more channels inoperable.
              ~JJ521 Dec l a r e associated          Immed i ately One or more                                            penet r ation flow path (s ) incapable of channels                                                automat i c isolation .
AA :r g qyi:rg g b¥-
inoperable.
ggqyi:rgg Ai;;ti9A  
Initiate action to              Immediately calcu l ate DRAIN TIME .
.a.A4 :rgfg:r9AQ9G.i-1:+  
G-... AA :rgqyi:rgd b¥-
~JJ521 G-... AA :rgqyi:rgd b¥-
ggqyi:rgd A i;;ti9A A..-+/-
ggqyi:rgd A i;;ti9A A..-+/-  
              .a.fi4 :f9f9:f9AQ9g .i-1:+
.a.fi4 :f9f9:f9AQ9g.i-1:+  
              ~JJ521 (co n tinued )
~JJ521 CLINTON REQUIRED ACTION
CLINTON                                        3 . 3 - 43a                           Amendment No. J.;b.
~
.t.f+/-. C9A9iti9A
:fQfQ:fQAQQg.i-1:+
~
J J 5 2 f.G-:r-
-t-M QAilAAQl Initiate action to place channel in trip.
Decl a r e associated penet r ation flow path (s ) incapable of automat i c isolation.
Initiate action to calcul ate DRAIN TIME.
3. 3-43a COMPLETION TIME Immediately Immedi ately Immediately (continued )
Amendment No. J.;b.  


RPV Water Inventory Contro l                Instrumentat i on f 3.3.5.2 ACTIONS         (cont i nued )
ACTIONS (conti nued )
CONDITION                             REQUIRED ACTION                            COMPLET I ON TIME
CONDITION  
~   Ag.   +/-:H'J:Hi+/-:@Q b¥             P-.-1. bl@G l ;;p: @ ~ "'.l'atE!m            .;i,. ~
~
g@qni+/-:E!Q AGtigi:i A-...l.                   ii:igp@ i::: eildl@
Ag. +/-:H'J:Hi+/-:@Q b¥ P-.-1.
      ~ +/-:E!fE!+/-:E!!=!GE! Q .i.f+
g@qni+/-:E!Q AGtigi:i A-...l.  
      ~           ~ ~ ~ 2 l           QR D--.- ~ -the-                ~ pYmp          .;i,. ~
~  
aHGtiQl=l .t..g. -the-
+/-:E!fE!+/-:E!!=!GE!Q.i.f+  
:;;ypp:i;9:;;:;; ,:i,gi:i ~
~  
E-.- Ag. :i;sqtii+/-:eci   b¥             E-.-J,. gs:;;tg i::: e Gfiirni:iel .t..g.      -64    ~
~  
ge q ti i:i; eg AGt i gi:i A-...l.           GJi!E gll £l1E :;;tatti:;;
~  
      ~ :i;efe:i;ei:iGeQ .i.f+
~ 2 l QR D--.- E-.-
      ~           ~ ~ ~ 2 l R.- geqni:i;sg AGt i gi:i ~             R.-J,. blsGlei i::: s a:;;:;;gGieiteg         Immegiatsl:i' ei:;;:;;gGieit@g                            ECC£. ii:i:j E!Gtigi:i ,l :;;p:i;ei J' Cgmpletigi:i Hme- G-f-                        :;;yld.s:i,:;;tem ii:igpe:i;aldle Cgi:ig i tigi:i c, .Q., G-+/-- E AG-t- me-t-.-
Ag. :i;sqtii+/-:eci b¥ E-.-J,.
CLINTON                                          3 . 3 - 43b                                   Amendment No.   ~
geq ti i:i;eg AGt i gi:i A-...l.  
~
:i;efe:i;ei:iGeQ.i.f+  
~  
~  
~  
~ 2 l R.- geqni:i;sg AGt i gi:i ~ R.-J,.
ei:;;:;;gGieit@g Cgmpletigi:i Hme-G-f-Cgi:ig i tigi:i c,.Q., G-+/-- E AG-t-me-t-.-
CLINTON RPV Water Inventory Control Instrumentati on f
3. 3. 5. 2 REQUIRED ACTION COMPLET I ON TIME bl@G l ;;p:@ ~
"'.l'atE!m
.;i,. ~
ii:igp@ i::: eildl@
~
-the- ~
pYmp
.;i,. ~
aHGtiQl=l.t..g. -the-
:;;ypp:i;9:;;:;;,:i,gi:i ~
gs:;;tg i:::e Gfiirni:iel.t..g.
-64 ~
GJi!Egll £l1E :;;tatti:;;
blsGlei i:::s a:;;:;;gGieiteg Immegiatsl:i' ECC£. ii:i:j E!Gtigi:i,l :;;p:i;ei J'
:;;yld.s:i,:;;tem ii:igpe:i;aldle 3. 3-43b Amendment No. ~  


These SRs apply to each Function in                                   RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 SURVE I LLANCE REQUIREMENTS
These SRs apply to each Function in RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 SURVE I LLANCE REQUIREMENTS  
          ---------------------------------- - -- NOTE ------------- - ------------------- - ---
----------------------------------- --NOTE-------------- -------------------- ---
Re-f.e.+/-- .t-G- Tab l e 3 . 3 . 5 . 2 - 1 .t-G- d e t e rmi1:rn ~ .£.Re. ~ .f.G+/-:. ~ EGG.£. F1m.::tig1=1 .
Re-f.e.+/--.t-G-Tabl e 3. 3. 5. 2 - 1.t-G-de t e rmi1:rn ~  
SURVEI LLANCE                                      FREQUENCY SR     3 . 3 . 5 . 2 .l   Perform CHANNEL CHECK .                                     I n accordance wi th t h e Surveil l ance Frequency Control Program SR     3.3.5.2.2         Perform CHANNEL FUNCT I ONAL TE ST .                         In accordance wit h the Surveil l ance Frequency Control Program CLINTON                                                3 . 3 - 43c                    Amendment No.   ~
.£.Re. ~  
.f.G+/-:. ~
EGG.£. F1m.::tig1=1.
SURVEILLANCE SR 3. 3. 5. 2.l Perform CHANNEL CHECK.
SR 3. 3. 5. 2. 2 Perform CHANNEL FUNCT I ONAL TEST.
CLINTON 3. 3-43c FREQUENCY I n accordance wi th t he Surveil l ance Frequency Control Program In accordance with the Surveil l ance Frequency Control Program Amendment No. ~  


RPV Water Inventory Contro l                                Instrumentat i on 3.3.5.2 Table 3 . 3 . 5 . 2 - 1 (page 1 of 2)
FUNCTION.-
RPV Water Inventory Control Instrumentation APPLICABLE                      CQNPITIQ11&#xa3; MODES OR      REQUIRED        l<li!:Fl!:l<l!:llC!W OTHER        CHANNELS              ERGM SPECIFIED          PER          l<l!:Ql!Il<l!:P      &#xa3;l!J<l11!:IbbMJCI!:                ALLOWABLE FUNCTION                CONDITIONS      FUNCTION        .ACTIQ~J A 1          l<l!:Q(!IJ<l!:Ml!:~JT:a'            VALUE
Jog11 Press" re Cggl:;rnt IHj e stiGH n (bPCI)
  .-  Jog11 Press " re Cggl:;rnt IHj e stiGH n (bPCI)
:oHGl 1.g" Pres:;;nPe Cgre  
:oHGl 1.g" Pres:;;nPe Cgre
&#xa3;pny (1-PC:a')
        &#xa3;pny (1-PC:a')
:a'nldsystem:;;
:a'nldsystem:;;
a-.-   !< e a st gr                                                                   .gg        ;;      2 1      f;    Hi4 p:;;ig u gggg l     Prge2rnrg                                                         .gg        ;;      2 2 1,gp (IHje stiGH Permi:;;:;;i" e)
a-.-
G-.-   bPC:a' PYmp                                                                   .gg        ;;      2 1      ;;; 72Q gpm bliscAargg Flgu                                                               .gg        ;;      2 2 1,gp   (llyp:o gg)
!< e a st gr u gggg l Prge2rnrg 1,gp (IHjestiGH Permi:;;:;;i" e)
G..-   bPCI Pnmp .A                                                                   .gg    d d        2 1      ;;; 9QQ gpm Pigsfis.rge &#xa5;12'7                                                             .gg    d d        2 2 bbl'! (ll yp* gg)
G-.-
  ~     bPCI !l aH9 bPCI C
bPC:a' PYmp bliscAargg Flgu 1,gp (llyp:o gg)
:a'uldi;;yi;;temg a-.- l<eastr;ir " egggl                                                               .gg    d d        2 1        f;  494 p:;;ig Pr988 " Hl       J,gp                                                         .gg    d d        2 2 (IHjestiGH Pgr:miggiug )
G..-
G-.-   1-PCI Pnmp !l                                                                 .gg    ;; d        2 1        ;;; 9QQ gpm
bPCI Pnmp.A Pigsfis.rge &#xa5;12'7 bbl'! (ll yp* gg)  
:OH9 1-PCI Pnmp C                                                             .gg    d d        2 2 Pisslnrge Fl2F -
~ bPCI !l aH9 bPCI C
:a'uldi;;yi;;temg a-.-
l<eastr;ir " egggl Pr988 " Hl J,gp (IHjestiGH Pgr:miggiug )
G-.-
1-PCI Pnmp !l
:OH9 1-PCI Pnmp C Pisslnrge Fl2F -
b2F (llypass)
b2F (llypass)
(continued)
RPV Water Inventory Contro l Instrumentat i on 3. 3. 5. 2 Table 3. 3. 5. 2-1 (page 1 of 2)
+ei+   Ass2si3tgg PitJ:1 3H !!:CC&#xa3; snldsystgm r:gqnir:gg tg }dg QPl!:l<A!lbl!: ldy bCQ d 3 2 ,                     " l'P" \l'J3tgr IHHQHtGP/
RPV Water Inventory Control Instrumentation APPLICABLE CQNPITIQ11&#xa3; MODES OR REQUIRED l<li!:Fl!:l<l!:llC!W OTHER CHANNELS ERGM SPECIFIED PER l<l!:Ql!Il<l!:P
Cgi:i.trg l "
&#xa3;l!J<l11!:IbbMJCI!:
CLINTON                                             3 . 3 - 43d                                                 Amendment No.               ~
ALLOWABLE CONDITIONS FUNCTION
.ACTIQ~J A 1 l<l!:Q(!IJ<l!:Ml!:~JT:a' VALUE
.gg 2 1 f; Hi4 p:;;ig
.gg 2 2
.gg 2 1
;;; 72Q gpm
.gg 2 2
.gg d d 2 1
;;; 9QQ gpm
.gg d d 2 2
.gg d d 2 1 f; 494 p:;;ig
.gg d d 2 2
.gg
;; d 2 1
;;; 9QQ gpm
.gg d d 2 2 (continued)  
+ei+
Ass2si3tgg PitJ:1 3H !!:CC&#xa3; snldsystgm r:gqnir:gg tg }dg QPl!:l<A!lbl!: ldy bCQ d 3 2,  
" l'P" \\l'J3tgr IHHQHtGP/
Cgi:i.trg l CLINTON 3. 3-43d Amendment No. ~  


RPV Water Inventory Contro l                                  Instrumentat i on 3.3.5.2 Table 3 . 3 . 5 . 2 - 1 (page 2 of 2)
FUNCTION Migl:! Press11re Cgre  
RPV Water Inventory Control Instrumentation APPLICABLE                              CQNblITIQN&#xa3; MODES OR            REQUIRED          Fli:Fli:Rli'.NCIW OTHER            CHANNELS                -FRGM SPECIFIED                PER            Fli:QTJIF!i:bl      &#xa3;TlF " li:IbPNC!i:                  ALLOWABLE FUNCTION                    CONDITIONS            FUNCTION         JlCTIQN Jl 1          Fli:QTJIF!i:Nli:NT&#xa3;                    VALUE
&#xa3;pr3y (MPC&#xa3;)  
  ;;...._  Migl:! Press11re Cgre
&#xa3;yste111 FCIC &#xa3;tgrage TaAk be" @l b9'!  
            &#xa3;pr3y (MPC&#xa3;) &#xa3;yste111
~ MPC&#xa3; Pn111p bl i sr;;l:iarge Pre a a" re Migl:!
            &-.-- FCIC &#xa3;tgrage TaAk             4 <b1 ,      a ''*                                      .&#xa3;R    -a-]~]"""-'~  2>-.-+/--1 be " @l       b9'!                                                                   .&#xa3;R    -a-]~]"""-'~  2~    2
            ~     MPC&#xa3; Pn111p                                                                           .&#xa3;R    ~:;~:;_...,.'"'"""2~1 bl i sr;;l:iarge                                                                       .&#xa3;R    .,,,
                                                                                                                  ] -.--a
                                                                                                                      ]-.-d~  2,.....-.=-
2 Pre a a " re       Migl:!
(llypns )
(llypns )
G-.- MPC&#xa3; &#xa3;yste111 Fl9H                                                                                           2 1            ~    ?QQ gpm F3te - b91' (llypns )
G-.-
RHR System Isolation
MPC&#xa3; &#xa3;yste111 Fl9H F3te -
: a. Reactor Vessel                       ( <> )        2 in one                                                  2 1          ::". 8.3 inches Water Level -                                         trip Low , Level 3                                       system Reactor Water Cleanup (RWCU) System
b91' (llypns )
                                              ~
RHR System Isolation a.
Isolation
Reactor Vessel Water Level -
: a. Reactor Vessel                       ( <> )       2 in one                                                 2 1           ::". - 48 . 1 Water Level - Low                                      trip                                                                inches Low , Level 2                                       system
Low, Level 3 Reactor Water Cleanup (RWCU) System Isolation a.
+a+       " ssssi3te9 11itl=l aA Rccg s11ssyste111 ret=J:11ireol ts loe QP!i:F " llbli: loy bCQ :;                   3 2,     " FP"     Water IA"eAte;sy C9Atrgl "
Reactor Vessel Water Level -
Wl=leA MPcg is QP!i:F " llbli: fgr G9111pliaAGe 11itl=l bCQ :; 3 2 , " FP" Water IA" eAtsry C9Atrsl , " aA9 aligAeol ts tl=le FCIC stsrage taAk 'll=lile taAk *1ater level is Ast 11itl=liA tl=le limits gf
Low Low, Level 2 RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 Table 3. 3. 5. 2 - 1 (page 2 of 2)
          &#xa3;F ]   a   2 ]
RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4 <b1, a''*
When automatic isolation of the associated penetration flow path(s)                                         is credited in calculating DRAIN TI ME .
(<> )  
CLINTON                                                             3.3 - 44                                                 Amendment No.               ~
~
(<> )
REQUIRED CHANNELS PER FUNCTION 2 in one trip system 2 in one trip system CQNblITIQN&#xa3; Fli:Fli:Rli'.NCIW
-FRGM Fli:QTJIF!i:bl JlCTIQN Jl 1  
&#xa3;TlF" li:IbPNC!i:
Fli:QTJIF!i:Nli:NT&#xa3;
.&#xa3;R
-a-]~]"""-'~2>-.-+/--
1
.&#xa3;R
-a-]~]"""-'~2~
2
.&#xa3;R
~:;~:;_...,.'"'"""2~1  
.&#xa3;R
] -.--a
]-.-d~2,.....-.=-
2 2 1 2 1 2 1 ALLOWABLE VALUE
~ ?QQ gpm
::". 8.3 inches
::". - 48. 1 inches
+a+  
" ssssi3te9 11itl=l aA Rccg s11ssyste111 ret=J:11ireol ts loe QP!i:F " llbli: loy bCQ :; 3 2,  
" FP" Water IA"eAte;sy C9Atrgl "
Wl=leA MPcg is QP!i:F " llbli: fgr G9111pliaAGe 11itl=l bCQ :; 3 2,  
" FP" Water IA" eAtsry C9Atrsl, " aA9 aligAeol ts tl=le FCIC stsrage taAk 'll=lile taAk *1ater level is Ast 11itl=liA tl=le limits gf  
&#xa3;F ] a 2 ]
When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TI ME.
CLINTON 3.3-44 Amendment No. ~  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS   (continued)
Primary Containment and Drywell Isolation Instrumentation 3. 3. 6. 1 ACTIONS (continued)
CONDITION                              REQUIRED ACTION          COMPLETION TIME J . As required by                     J .l      Isolate the affected    24 hours Required Action F . l                       penetration flow and referenced in                           path (s) .
J.
Table 3 . 3 . 6 . 1 - 1 .
K.
K. As required by                     K. l      Be in MODE 3 .          12 hours Required Action F . l and referenced in                 AND Table 3 . 3 . 6.1 - 1 .
L.
K. 2      Be in MODE 4 .          36 hours OR Required Act i on and associated Completion Time of Condition I or J not met.
M.
L. As required by                     L. l       Declare associated      1 hour Required Action F . l                       standby liquid and referenced in                           control subsystem Table 3 . 3 . 6 . 1 - 1 .                   inoperable .
CONDITION As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.
OR L.2       Isolate the Reactor     1 hour Water Cleanup System .
As required by Required Action F. l and referenced in Table 3. 3. 6.1 - 1.
M. As required by                    M. l      Initiate action to     Immediately Required Action F . l                        restore channel to and referenced in                          OPERABLE status .
OR Required Act i on and associated Completion Time of Condition I or J not met.
Table 3 . 3 . 6 . 1 - 1 .
As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.
IHitiate aGtiGH .t4     Immeciiately isGlate ~ 1;:es i cilnl
As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.
                                                  ~ 1;:e1+18''a l ~
CLINTON J. l K. l AND K. 2 L. l OR L. 2 M. l REQUIRED ACTION Isolate the affected penetration flow path (s).
                                                  &#xa3;l::wtciGHH CGGliHg
Be in MODE 3.
                                                  &#xa3;ystem snGtiGH ~
Be in MODE 4.
                                                  ~ re21GtGr " essel (continued)
Declare associated standby liquid control subsystem inoperable.
CLINTON                                      3.3 - 51                     Amendment No. ~
Isolate the Reactor Water Cleanup System.
Initiate action to restore channel to OPERABLE status.
IHitiate aGtiGH.t4 isGlate ~
1;:es i cilnl  
~
1;:e1+18''a l ~  
&#xa3;l::wtciGHH CGGliHg  
&#xa3;ystem snGtiGH ~  
~
re21GtGr "essel 3.3-51 COMPLETION TIME 24 hours 12 hours 36 hours 1 hour 1 hour Immediately Immeciiately (continued)
Amendment No. ~  


Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION                              REQUIRED ACTION                        COMPLETION TIME M.     (Continued)                               Initiat g aQtign .t4 rgstgrg SQQgndary Qgnt;;iinmgnt .t4 QPJi:'.RAJ3I.E: steitns Initiat g aQtign .t4 r g stgr g    '     standay ga.& trgatmgnt ~
Primary Containment and Drywell Isolation Instrumentation 3. 3. 6. 1 ACTIONS M.
s agyst:gm .t4 QPE:RAJ3I.E:
N.
11 status Initiat g aQtign .t4 rgstgrg isglatign Qapaaility .i.A ~
CONDITION (Continued)
r9b{ irgd SQQgnd;;iry 11 Qgntainm g nt 6-00 s g Qgndary Qgntainm g nt aypass p g n g tratign
As required by Required Action F. l and referenced in Table 3. 3. 6. 1 - 1.
                                                  ~         pa-th A-G-t-is g lat 9 d M.--J-.                   NQ TE:
CLINTON REQUIRED ACTION Initiatg aQtign.t4 rgstgrg SQQgndary Qgnt;;iinmgnt.t4 QPJi:'.RAJ3I.E: steitns Initiatg aQtign.t4 r gstgrg ' standay ga.& trgatmgnt ~
E+l-t-Pf aH-G   ~     -i-&
s 11agyst:gm.t4 QPE:RAJ3I.E:
pgrmissiblg .um:ie-r-administratiug Qm:1trgl Initiat g aQtign .t4                 Imm g diat g ly
status Initiatg aQtign.t4 rgstgrg isglatign Qapaaility.i.A ~
                                                  -G-1-G-&e- '     OOG-r- .i.A -t-fi.e-
r9b{ 11 irgd SQQgnd;;iry Qgntainmgnt 6-00 s g Qgndary Qgntainmgnt aypass p g n g tratign  
                                                  .uppe-r. Qgntainmgnt pgrsgnngl d-i+/--         ~
~
N. As required by                N. 1          Isolate the affected                 Immediately Required Action F . l                      penetration flow and referenced in                          path (s).
pa-th A-G-t-is g lat 9 d M.--J-. NQ TE:
Table 3 . 3 . 6 . 1 - 1 .
N. 1 OR N. 2 E+l-t-Pf aH-G ~  
OR N. 2          Suspend movement of                 Immediately recently irradiated fuel assemblies in the primary and secondary containment.
-i-&
CLINTON                                      3.3 - 52                                   Amendment No. ---2-1-e.
pgrmissiblg.um:ie-r-administratiug Qm:1trgl Initiatg aQtign.t4  
-G-1-G-&e- '
OOG-r-.i.A -t-fi.e-
.uppe-r. Qgntainmgnt pgrsgnngl d-i+/-- ~
Isolate the affected penetration flow path (s).
Suspend movement of recently irradiated fuel assemblies in the primary and secondary containment.
3.3-52 COMPLETION TIME Immgdiatg ly Immediately Immediately Amendment No. ---2-1-e.  


LOP Instrumentat i on 3.3.8.1 3.3  I NSTRUMENTATION 3.3.8.1   Loss of Power (LOP ) Instrumentation LCO 3.3.8.1       The LOP i nstrumentation for each Function in Tab l e 3 . 3 . 8 . 1 - 1 shal l be OPERABLE.
3. 3 I NSTRUMENTATION 3. 3. 8. 1 Loss of Power (LOP ) Instrumentation LOP Instrumentati on 3. 3. 8. 1 LCO 3. 3. 8. 1 The LOP i nstrumentation for each Function in Tab l e 3. 3. 8. 1-1 shal l be OPERABLE.
APPLICABIL I TY :     MODES 1 , 2 , and 3,             ~
APPLICABIL I TY :
Wfi.e-A .:l;.l:i.e aeeocia.t e d di e s e l g e n e ra.tor ~ .i.& r e qtJ.ir e d .t.G b.e-OP:E;g7\fl1.8 b:f I.W ~ g ~ , .'.!.AG &#xa3;onrc e s - &#xa3;J:rntdoun "
MODES 1, 2, and 3, ~
ACTIONS
Wfi.e-A.:l;.l:i.e aeeocia.te d di e s e l ge n e ra.tor ~  
------------------------------------- NOTE -------------------------------------
.i.& r e qtJ.ire d.t.G b.e-OP:E;g7\\fl1.8 b:f I.W ~ g  
Separate Condition entry is al l owed for each channel .
~
CONDITION                                 REQUIRED ACTION                   COMPLETION TIME A. One or more channels               A. 1   Place channel in trip .             1 hour inoperable .
.'.!.AG &#xa3;onrce s - &#xa3;J:rntdoun "
AND A. 2   --------- NOTE ----------
ACTIONS  
On l y applicable for Funct i ons 1. c , 1 . d ,
-------------------------------------NOTE-------------------------------------
1 . e , 2 . c , 2 . d , and 2.e Restore channel to OPERABLE stat u s .                 7 days B. Required Act i on and               B. l   Declare associated DG               Immediately associated Completion                       inop erable .
Separate Condition entry is al l owed for each channel.
Ti me not met .
CONDITION REQUIRED ACTION COMPLETION TIME A.
CLINTON                                       3.3 - 78                               Amendment No.         ~
One or more channels A. 1 Place channel in trip.
1 hour inoperable.
AND A. 2  
---------NOTE----------
On l y applicable for Funct i ons 1. c, 1. d,
1. e, 2. c, 2. d, and 2. e Restore channel to OPERABLE statu s.
7 days B.
Required Act i on and B. l Declare associated DG Immediately associated Completion inoperable.
Ti me not met.
CLINTON 3.3-78 Amendment No. ~  


AC   Sources ~ S hu tdown 3.8.2 SURVE I LLANCE REQUIREMEN TS SURVEI LLANCE                                        FREQUENCY SR 3.8.2.l       ------------------- NOTE --------------------                   , SR 3.8.1.10,
AC Sources ~ S hu tdown 3. 8. 2 SURVE I LLANCE REQUIREMENTS SURVEILLANCE SR 3. 8. 2. l  
                                                                                  .Jt:!
-------------------NOTE--------------------
                                                                                        ~
The fol l owing SRs are not required to be.Jt:!
Th e fol l owing SRs are not re q uired to be per f ormed : SR 3.8 . 1.3 , SR 3 . 8 . 1.9 through             SR 3.8.1.14, and
per f ormed :
                            $R ~ g l ll , $R J g l u               through SR 3 . 8 . 1 . 16, 6-AG $R J g l a .
SR 3.8. 1.3, SR 3. 8. 1.9 through  
                                                                                        --0 The fol lowing SRs    ~~           AC sources required to be           OPERABLE~       I n accordance are app licable for         &#xa3;.R.g. ~ &#xa3;pg,-;ifi&#xa3;atioi:i J g l,         gxggpt             with appl i cable
$R ~ g l ll, $R J g l u through SR 3. 8. 1. 16, 6-AG $R J g l a.
                            $R ~   g l   g , $R J g l 16 , $R J g l       17 '       SRs
lowing SRs The fol are app
                            $R ~   g l   lg , 6-AG $R J g l 6Q a-re appli.-;afile SR 3.8.1 .1                 SR 3.8.1 .6 SR 3.8.1 .2                 SR 3.8.1 .9 SR 3.8.1 .3                 SR 3.8.1 .10 SR 3.8.1.4                 SR 3.8.1 .14 SR 3.8.1 .5                 SR 3.8.1 .16 CLINTON                                           3 . 8- 19                   Amendment No.   ~
~  
~
AC sources required to be OPERABLE~
licable for  
&#xa3;.R.g. ~ &#xa3;pg,-;ifi&#xa3;atioi:i J g l, gxggpt  
$R ~ g l g, $R J g l 16, $R J g l 17 '  
$R ~ g l lg, 6-AG $R J g l 6Q a-re appli.-;afile SR 3.8.1.1 SR 3.8.1.6 SR 3.8.1.2 SR 3.8.1.9 SR 3.8.1.3 SR 3.8.1.10 SR 3.8.1.4 SR 3.8.1.14 SR 3.8.1.5 SR 3.8.1.16 CLINTON 3. 8-19 FREQUENCY
~
, SR 3.8.1.10, SR 3.8.1.14, and
--0 I n accordance with appl i cable SRs Amendment No. ~  


ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.6.1.3-5 3.8.2-3
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.6.1.3-5 3.8.2-3  


Definitions
Definitions
: 1. 1 1.1 Definitions     (continued)
: 1. 1 1.1 Definitions (continued)
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 closed and administratively controlled Dresden 2 and 3 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 . &sect; ., seismic eveAt ,
The water inventory above the TAF is divided by the limiting drain rate;
l oss of Aorrna l po *.1er , siA&sect;le hbtrnaA error) ,
: 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. &sect;., seismic eveAt,
l oss of Aorrna l po*.1er, siA&sect;le hbtrnaA error),
for all penetration flow paths below the TAF except:
for all penetration flow paths below the TAF except:
Penetration flow paths connected to an closed and                                intact closed system, or isolated by administratively controlled                manual or automatic valves that are l ocke9 , sea l e9 , or other **i se seCb1re8 in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration fl ow paths;
Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are l ocke9, sea l e9, or other* *i se seCb1re8 in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration fl ow 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
: 2.
: 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 device without offsite power.
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
(continued)
: 3.
Dresden 2 and 3                          1.1-4                   Amendment No. 266/259
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 device without offsite power.
(continued) 1.1-4 Amendment No. 266/259  


RPV Water I nventory Contro l I nstrumentation
3.3 I NSTRUMENTATION RPV Water Inventory Contro l Instrumentation 3.3. 5. 2 3.3.5.2 Reactor Pressure Vesse l (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentation for each Funct i on in Table 3.3.5.2-1 sha l l be OP ERABLE.
: 3. 3. 5. 2 3.3      I NS TRUMENTATION 3.3 . 5.2         Reactor Pressure Vesse l (RPV) Water I nventory Control I nstrumentation LCO       3.3.5.2                 The RPV Water Inventory Contro l instrumentation for each Funct i on in Table 3.3.5.2-1 sha l l be OP ERABLE.
AP PLI CAB ILITY:
AP PLI CAB ILIT Y:               According to Tab l e 3.3.5.2-1.
According to Tab l e 3.3.5.2-1.
ACTIONS
ACTIONS  
      - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Cond i tion entry is al lowed for each channe l .
A.On in ope Separate Cond i tion entry is al lowed for each channe l.
CON DIT ION                                               REQU I RED AC TI ON                     COM PLE TI ON TI ME A.-     GAe OF Arn Fe           GAflAAe~     s         A--.+/--               E:A teF tl:le 6oA9itioA             I11m1e9i ete~ J' iAOFJeFaB~e .                                                        Fef:eFeAGe9 i A
CON DIT ION REQU I RED AC TI ON COM PLETI ON TI ME A.-
                                                                                      +a t:i~e J . J . a . ~ 1 f:OF tRe GAaAAe~ .
GAe OF Arn Fe GAflAAe~ s A--.+/--
A.1           I
E:A teF tl:le 6oA9itioA I11m1e9i ete~ J' iAOFJeFaB~e Fef:eFeAGe9 i A  
                                                                  \&#xa5;
+a t:i~e J
        .g.._   As                     BJ'                     .g....,..+           I nitiate act i on to               Immediately
. J
        \
. a
Fe~tJiFe9 Re~tJi   Fe9 AGtiOA A. 1                                           place channe l in a Ag Fef:eFeAGe9 i A                                                 trip .
. ~ 1 f:OF A.1 I tRe GAaAAe~
                +at:i ~e   J . J . a . ~   1.
\\&#xa5;  
OR                     IA.2.1 I it   Dec l are associated                  Immediately A.On e or more channels                                         ~
.g.._
in ope rable.                                                                         penetration fl ow path(s) incapable of automatic iso l ation.
As Fe~tJiFe9 BJ'  
.g....,..+
Initiate act i on to Immediately  
\\
Re~tJi Fe9 AGtiOA A. 1 place channe l in a Ag Fef:eFeAGe9 i A trip.  
+at:i ~e J
. J
. a
. ~ 1.
OR IA.2.1 I it e or more channels  
~
Dec l are associated Immediately rable.
penetration fl ow path(s) incapable of automatic iso l ation.
A~
A~
B.2 . 2             I nitiate action to                 Immediately ca l cu l ate DRAIN TIM E.
B.2. 2 Initiate action to Immediately ca l cu l ate DRAIN TIM E.
6 . As     Fe~tJi   Fe9 gJ1                           b----.----+/--     i:n aGe   GAaAAe~       i A tFiFJ . 1 AOLiF Re~tJiFe9         AGtioA A. 1 fJA9 Fef:eFeAGe9 i A
: 6. As Fe~tJi Fe9 gJ1 b----.----+/--
              +at:i~e J . J . a . 2 1.
i:n aGe GAaAAe~ i A tFiFJ.
1 AOLiF Re~tJiFe9 AGtioA A. 1 fJA9 Fef:eFeAGe9 i A  
+at:i~e J.J. a. 2 1.
(cont i nued)
(cont i nued)
Dresden 2 and 3                                                           3.3 . 5. 2-1                         Amendment No . 2&sect;g/2&sect;1
Dresden 2 and 3 3.3.5. 2-1 Amendment No. 2&sect;g/2&sect;1  


RPV Water I nventory Contro l I nstrumentation
RPV Water Inventory Contro l Instrumentation 3.3. 5. 2 ACTIONS COND IT ION REQUIRED ACTION COMP LETI ON TI ME Q. As FeEjtii reEI B:J'  
: 3. 3. 5. 2 ACTIONS COND IT ION                                           REQUIRED ACTION                             COMP LETI ON TI ME Q. As FeEjtii reEI B:J'                             .IJ-.--+/-. Restere GRannel te                           24 R8blFS ReEjti ire El AGtien A. 1                                     OPrnAgLE stattis .
.IJ-.--+/-.
a nEI ref:erenGeEI in
Restere GRannel te 24 R8blFS ReEjti ire El AGtien A. 1 OPrnAgLE stattis.
          +:a8le ~ . ~ . 9 . 2 1.
a nEI ref:erenGeEI in  
E. ReEjti ire El AGtien a nEI                           -h       IJeGlare asseGiateEI l ei,1                   +/-mmeEli atel:J' asseGiateEI 6emf)letien                                       flFesstire E66&#xa3;
+:a8le  
          +:ime ef: 6enElitien 6 8F                                     i naeGti en,LSfJFa:J' Q net met.                                                     SblBS:J' Stem inef)eFa8le .
~
SURV EILL ANCE REQUIR EMENTS
. ~
. 9
. 2 1.
E. ReEjti ire El AGtien a nEI  
-h IJeGlare asseGiateEI l ei,1  
+/-mmeEli atel:J' asseGiateEI 6emf)letien flFesstire E66&#xa3;  
+:ime ef: 6enElitien 6 8F i naeGti en,LSfJFa:J' Q net met.
SblBS:J'Stem inef)eFa8le.
SURV EILLANCE REQUIR EMENTS  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
~These SRs apply to each Function in I
~These SRs apply to each Function in I
  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Ref:er te Tab l e 3.3.5.2-1 te Eletermine 11RiGR &#xa3;Rs af)fllY f:er eaGR E66&#xa3;  
Ref:er te Tab l e 3.3.5.2-1 te Eletermine 11RiGR &#xa3;Rs af)fllY f:er eaGR E66&#xa3; ~tinGtien .
~tinGtien SURVEI LLANC E SR 3.3.5. 2.1 Perform CHANNE L CHECK.
SURVEI LLANC E                                                             FR EQUENCY SR     3 . 3.5 . 2. 1           Perform CHANNE L CHECK .                                                         In accordance with the Survei l lance Frequency Contro l Program SR     3 . 3 . 5.2.2             Perform CHANNE L FUNC TI ONAL TE ST.                                             I n accordance wi t h the Survei l lance Frequency Contro l Program Dresden 2 and 3                                                     3.3 . 5. 2-2                           Amendment No . 268/261
SR 3.3.5.2.2 Perform CHANNE L FUNCTI ONAL TEST.
Dresden 2 and 3 3.3.5. 2-2 FREQUENCY In accordance with the Survei l lance Frequency Contro l Program In accordance wi t h the Survei l lance Frequency Contro l Program Amendment No. 268/261  


RPV Water I nventory Contro l I nstrumentation
FUNCTION  
: 3. 3. 5. 2 Table 3 . 3 . 5 . 2-1 (Page 1 of lJ RPV Water Inventory Control Instrumentation APPLICABLE                                bGNl:llTIGMS MODES                                  R>*rnrnGrn OR OTHER                REQUIRED            ~
~ ReaGter Steam Geme Press~re be11 (Permissi,,e)
SPECIFIED            CHANNELS PER          R>Q " IRrn  SllR" U bb ' MG>              ALLOWABLE FUNCTIO N                  CONDITIONS                FUNCTION         ' bTIG~I  0
B-.
                                                                                                      .1 R>Ql lIR>MDIH                      VALUE
Gere S~ray P61m~
        ~     ReaGter Steam Geme                                                                       ~    L~ . 9 . 2 . 2      ,,; ;J41.7  ~sig Press~re be11 (Permissi,,e)
G i s>:~arge
B-. Gere   S~ray   P61m~                                       ~                            ~    :i . :i . 8 . 2 . 2 G i s>:~arge
* l e" be11 rn) ~a66 l be11 Prsss *1rs Geel a Rt IRjeGtieR (bPG I ) Systsm  
* l e" be11                                 ~ 1 1m~ (al rn)   ~a66 l
~  
  ,..___  be11 Prsss *1rs Geel a Rt IRjeGtieR (bPG I ) Systsm
~  
        ~     ReaGter Steam Geme                                                                        ~    ;J.:J.9.2.2        ,,; ;J41.7  ~sig Prsss~re be11 (Psrmissi,,e) be1 I Press 11re Geel a Rt
{)...                                    4-,----4                ~                              ~     ;i . ;i . 9. 2. 2      llG?  g~m IRjeGtieR P11m~                                          lee~ ( 3)
GiSGRarge
* 1e1 I be11
~
~
rny~ass)
4-.
  ~      Shutdown Cooling System (SOC) Isolation a . Reactor Vessel Water
~ ReaGter Steam Geme Prsss~re be11 (Psrmissi,,e)
                                              ~   ( {} )                 per trip                       ~     ;i . ;i . 9. 2. i  ~   2 . 65 inches Level-Low                                                system                        ~     ;i . ;i . 9. 2. 2
{)...
~ 4-. Reactor Water Cleanup System Isolation
be1 I Press 11re Geel a Rt IRjeGtieR P11m~
: a. Reactor Vessel Water
GiSGRarge *1 e1 I be11 rny~ass)
                                              ~   ( {} )                per trip                      ~    ;i . ;i . 9. 2. 1  ~   2 . 65 inches Level-Low                                                  system                        ~     ;i . ;i . 9. 2. 2 0
Shutdown Cooling System (SOC) Isolation
sseGiate9 " itR aR       .:u:s s~9system   re~~ireEJ te 9e GP>R ' H> 9y u:G :l . 9 . 2 , " RP " 'later IR"eRtery (;eRtrel ."
: a. Reactor Vessel Water Level-Low Reactor Water Cleanup System Isolation
When automatic i solation of the associated pene t ration flow path(sJ is credited in calculat i ng DRAIN TIME .
: a.
Dre sden 2 and 3                                                   3 .3 . 5 . 2-3                         Amendment No . 256 / 249
Reactor Vessel Water Level-Low RPV Water Inventory Contro l Instrumentation
: 3. 3. 5. 2 Table 3. 3. 5. 2-1 (Page 1 of lJ RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4-,----4
~
( {} )  
~
( {} )
REQUIRED CHANNELS PER FUNCTION
~
~
1 1m~ (al
~
lee~ ( 3) per trip system per trip system bGNl:llTIGMS R>*rnrnGrn
~
R>Q" IRrn SllR" U bb ' MG>
' bTIG~I 0. 1 R>Ql lIR>MDIH
~ L~
. 9
. 2
. 2
~ :i. :i. 8. 2. 2
~ ;J.:J.9.2.2
~ ;i. ;i. 9. 2. 2  
~ ;i. ;i. 9. 2. i
~ ;i. ;i. 9. 2. 2
~ ;i. ;i. 9. 2. 1
~ ;i. ;i. 9. 2. 2 ALLOWABLE VALUE
,,; ;J41.7 ~sig
,,; ;J41.7 ~sig llG? g~m
~ 2. 65 inches
~ 2. 65 inches 0 sseGiate9 " itR aR.:u:s s~9system re~~ireEJ te 9e GP>R ' H> 9y u:G :l. 9. 2, " RP " 'later IR"eRtery (;eRtrel."
When automatic i solation of the associated penet ration flow path(sJ is credited in calculat i ng DRAIN TIME.
Dresden 2 and 3 3.3. 5. 2-3 Amendment No. 256 / 249  


LOP Instrumentation 3.3.8.1 3.3       INSTRUMENTATION 3.3.8.1           Loss of Power (LOP) Instrumentation LCO     3.3.8.1                 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LOP Instrumentation 3.3.8.1 LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
APPLICABILITY:                   MODES 1, 2, and 3,
APPLICABILITY:
                                  '1Jf1 e A
ACTIONS MODES 1, 2, and 3, ~
                                                                        ~
'1Jf1 e A Hie assoc i ate El Eli es el
Hie assoc i ate El Eli es e l &sect; e A et'' at o I" i s I" e q 1:.d I" e El to 13 e OPERABLE B)' LCO 3. 8 . 2, " AC Sotll"ces SFiutElo 'vJA ."
&sect; e A et'' at o I" i s I" e q 1:.d I" e El to 13 e OPERABLE B)' LCO 3.8. 2, " AC Sotll"ces SFiutElo'vJA."  
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is all owed for each channel.
Separate Condition entry is all owed for each channel.
CONDITION                                             REQUIRED ACTION                             COMPLETION TIME A.     One or more channels                           A.1             Place channel in                           1 hour inoperable.                                                     trip.
CONDITION REQUIRED ACTION COMPLETION TIME A.
B.     Required Action and                             B.1             Declare associated                         Immediately associated Completion                                           diesel generator (DG)
One or more channels A.1 Place channel in 1 hour inoperable.
Time not met.                                                   inoperable.
trip.
Dresden 2 and 3                                                     3.3.8.1-1                               Amendment No. 185/180
B.
Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)
Time not met.
inoperable.
Dresden 2 and 3 3.3.8.1-1 Amendment No. 185/180  


PC I Vs 3 . 6 .1. 3 AC TIONS CON DIT ION                   REQUIR ED AC TIO N                        COM PLETI ON TI ME
ACTIONS CON DIT ION
: c.   (con t inued)               C. 2     - - - - - - - -NO TE S- - - - - - - -
: c.
: 1. I so l ation devices in hi gh rad i ation areas may be veri f ied by use of adm i ni strative means.
(cont inued)
: 2. I so l ation devices t hat a re a l ocked, sea l ed, or otherwise secured may be verified by use of ad mi nistrative means .
C. 2 D.
Ver i fy the affected                   Once per 31 days penetrat i on fl ow path is i so l ated.
MS IV lea kage ra t e D. 1 not wit hin l imit.
D. MS I V lea kage ra t e      D. 1      Restore leakage ra t e                   8 hours not wit hin l im it.                  to wit hin l i mit .
E.
E. Requ i red Ac ti on and    E. 1      Be i n MOD E 3.                         12 hours assoc i ated Comp l et i on Ti me of Cond iti on A,    AND B' C, or D no t met ..:i-A-MQg~
Requ i red Acti on and E. 1 assoc i ated Comp l et i on Ti me of Cond iti on A, AND B' C, or D not met..:i-A-MQg~ +/-' 2 ' 8F d.
            +/-' 2 ' 8F d .        E. 2      Be i n MODE 4.                           36 hours Dresden 2 and 3                        3 . 6.1.3-5                               Amendment No . 256 / 249
E. 2 Dresden 2 and 3 REQUIR ED ACTIO N
- -- - - - - -NOTES- - - - - - - -
: 1.
I so l ation devices in hi gh rad i ation areas may be veri f ied by use of admi ni strative means.
: 2.
I so l ation devices t hat a re a l ocked, sea l ed, or otherwise secured may be verified by use of admi nistrative means.
Ver i fy the affected penetrat i on fl ow path is i so l ated.
Restore leakage ra t e to wit hin l i mit.
Be i n MOD E 3.
Be i n MODE 4.
PC I Vs 3. 6.1. 3 COM PLETI ON TI ME Once per 31 days 8 hours 12 hours 36 hours 3. 6.1.3-5 Amendment No. 256 / 249  


AC Sources-Shutdown 3.8.2 ACTIONS CONDITION                                       REQUIRED ACTION                              COMPLETION TIME B. One required DG                         B.1           Suspend CORE                               Immediatel y inoperable.                                            ALTERATIONS.
ACTIONS CONDITION B.
B.2            Suspend movement of                       Immediatel y recently irradiated fuel assemblies in secondary containment.
One required DG inoperable.
B.3            Initiate action to                         Immediately restore required DG to OPERABLE status.
B.1 B.2 B.3 REQUIRED ACTION Suspend CORE ALTERATIONS.
SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1 .17.
Suspend movement of recently irradiated fuel assemblies in secondary containment.
SURVEILLANCE REQUIREMENTS FREQUENCY
Initiate action to restore required DG to OPERABLE status.
                                                                                                                                      -+
AC Sources-Shutdown 3.8.2 COMPLETION TIME Immediatel y Immediatel y Immediately SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.
SR   3.8.2.1       - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - -
SURVEILLANCE REQUIREMENTS SR 3.8.2.1  
The followi g SRs are not required to performed: r~~r.--...+-.--T.---2M+--'7-.e-.--:r--.--:+/-:-1::1----t-tt-H::H:ttl-ft t
- - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - -
                              ~R   2 . g . 1 . 12 , ane       ~R   2 . g . 1 . 14 thro~gh
The following SRs are applicable for The followi g SRs are not required to performed: r~~r.--...+-.--T.---2M+--'7-.e-.--:r--.--:+/-:-1::1----t-tt-H::H:ttl-ft  
                              ~R   2 . g . i. rn .
~R 2. g. 1. 12, ane  
The following SRs    i------+ ~ AC         sources required to be OPERABLE                                       In accordance are applicable for            ~Rs     of   ~pecification             2 . g . 1 , except                         with applicable
~R 2. g. 1. 14 thro~gh  
                              ~R   2 . g . 1 . 9 , ~R 2 . g . 1 . 12 , ~R 2 . g . 1 . 19 ,                       SRs
~R 2. g. i. rn.
                              ~R   2 . g . 1 . 20 , ane ~R 2 . g . 1 . 21 are applica8 l e .
i------+ ~
SR 3.8.1.1                 SR     3.8.1.6 SR 3.8.1.2                SR     3.8.1.10 SR 3.8.1.3                SR     3.8.1.11 SR 3.8.1.4                SR     3.8.1.15 SR 3.8.1.5                SR     3.8.1.17 Dre sden 2 and 3                                         3 .8.2-3                               Amendment No. 26g/26 1
AC sources required to be OPERABLE  
~Rs of ~pecification 2. g. 1, except  
~R 2. g. 1. 9,  
~R 2. g. 1. 12,  
~R 2. g. 1. 19,  
~R 2. g. 1. 20, ane  
~R 2. g. 1. 21 are applica8 l e.
SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.15 SR 3.8.1.17 FREQUENCY In accordance with applicable SRs Dresden 2 and 3 3.8.2-3 Amendment No. 26g/26 1  
-+
t


ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.5.2-4 3.3.6.1-4 3.3.8.1-1 3.5.1-1 3.5.1-2 3.5.2-2 3.5.2-3 3.5.2-5 3.8.2-4
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.5.2-4 3.3.6.1-4 3.3.8.1-1 3.5.1-1 3.5.1-2 3.5.2-2 3.5.2-3 3.5.2-5 3.8.2-4  


Definitions
1.1 Definitions DOSE EQUIVALENT I-131 (continued)
: 1. 1 1.1  Definitions DOSE EQUIVALENT I-131 30, Supplement to Part 1, pages 192-212, Table (continued)        titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."
DRAIN TIME closed and administratively controlled LaSalle 1 and 2 Definitions
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:
: 1. 1 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."
: a. The water inventory above the TAF is divided by the l imiting drain rate;
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:
: b. The lim i ting 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 dra i n rates through multiple penetration flow paths susceptible to a common mode failu re (e . g ., seismic event , loss of normal
: a.
                                ~0 .1er , single ~u1man error) , for all 1
The water inventory above the TAF is divided by the l imiting drain rate;
penet rat ion flow paths below the TAF except:
: b.
: 1. Penetration flow paths connected to an closed and administratively          intact closed system, or isolated by manual or automatic valves that are controlled l ocked , sea l ed , or 0H1ernise seCblred in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
The limi ting 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 dra i n rates through multiple penetration flow paths susceptible to a common mode failu re (e. g., seismic event, loss of normal  
: 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 (continued)
~0 1.1er
LaSalle 1 and 2                    1.1-4                   Amendment No. 242/228
, single  
~u1man error), for all penet rat ion flow paths below the TAF except:
: 1.
Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are l ocked, sea l ed, or 0H1ernise seCblred 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 (continued) 1.1-4 Amendment No. 242/228  


RPV Water Inventory Control Instrumentation -+-
3.3 INSTRUMENTATION 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.
: 3. 3. 5. 2 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:
A.1 Initiate action to place
ACTIONS According to Table 3.3.5.2-1.
                                          -    channel in trip.
A.1 Initiate action to place channel in trip.
ACTIONS                                        OR
OR  
                                            - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is a lowed for each channel.
Separate Condition entry is a lowed for each channel.
CONDITION                             REQUIRED ACTION                                COMPLETION TIME                I
CONDITION  
  -A-o-   0Ae or more cAaAAels                           EAter tAe CoAElitioA                        Imme Eli a tel :Y iAoperable .                                   referCAced i A Taele 3. 3. 5. 2 1 for A. One or more                             tAe cAaAAel .                                \!Immediately I
-A-o-0Ae or more cAaAAels iAoperable.
          ;-channels
A. One or more  
-    -r+----i IV inoperable.                                                                               '+'
;-channels  
  -&-;-    As reEJt:li reEl by                             Declare associated                          Immediately ReEjuireEl ActioA A. 1                         penetration flow aAEl refereAceEl iA                             path(s) incapable of Taele 3. 3 . 5. 2 1.                           automatic isolation.
-r+----i IV inoperable.
( ~A N~
As reEJt:li reEl by ReEjuireEl ActioA A.1 aAEl refereAceEl iA Taele 3.3. 5. 2 1.
IQ-/ ,.         r     Initiate action to calculate Calculate DRAIN TIME.
REQUIRED ACTION EAter tAe CoAElitioA referCAced i A Taele 3.3. 5. 2 1 for tAe cAaAAel.
IA.2.2:t---.~B-:                                                       Immediately C. As reEJui red by                                 Place cAaAAel iA trip .                        1 ROUP ReEjui r eEl ActioA A. 1 aAEl refereAceEl iA Table 3 . 3 . S. 2 1.
Declare associated penetration flow path(s) incapable of automatic isolation.
(continued)
( ~A N~ Initiate action to IQ-/,. r calculate IA.2.2:t---.~ B-: Calculate DRAIN TIME.
LaSalle 1 and 2                                     3.3.5.2-1                                 Amendment No. 230/216
C. As reEJui red by ReEjui r eEl ActioA A. 1 aAEl refereAceEl iA Table 3.3.S. 2 1.
Place cAaAAel iA trip.
COMPLETION TIME I
Imme Eli a tel :Y
\\!Immediately I
'+'
Immediately Immediately 1 ROUP (continued)
LaSalle 1 and 2 3.3.5.2-1 Amendment No. 230/216  


RPV Water In ventory Control In strumentation ~
RPV Water In ventory Control In strumentation ~
3.3 .5 .2 AC TION S         (continued)
3.3.5.2 ACTION S (continued)
CONDITION                                           REQUIRED AC TIO N                                 COMPLETION TIME B. ,ais FeEf td Fee B:Y                           B-:-+         Res=!:sFe eFiaAAel =!:s                         24   AS~FS ReEf~i Fee ,o,e=t:i SA A . 1                               OPERABLE s=!:a=!:~s .
CONDITION REQUIRED ACTIO N COMPLETION TIME B.,ais FeEf td Fee B:Y B-:-+
a AEl Fefe FeAeeEl i A
Res=!:sFe eFiaAAel =!:s 24 AS~FS ReEf~i Fee,o,e=t:i SA A. 1 OPERABLE s=!:a=!:~s a A El Fefe FeAeeEl i A  
        =Fasl e 3 . 3 . 5 . 2 1.
=Fasl e 3. 3. 5. 2 1.
E. ReEJ~i Fee P.c=!:i SA a AS                   f-:-1.       Beel a Fe asssci a=!:ee                         Ifflffleei a=!:el y asssei a=!:ee                                             EGGS i Aj ee=!:i SA 1ls13 Fa :y Gsfflp le=!: i SA =Fiffle sf                               s~ssys=!:effl iAspeFasle .
E.
ReEJ~i Fee P.c=!:i SA a AS f-:-1.
Beel a Fe asssci a=!:ee Ifflffleei a=!:el y asssei a=!:ee EGGS i Aj ee=!:i SA 1ls13 Fa:y Gsfflp le=!: i SA =Fiffle sf s~ssys=!:effl iAspeFasle.
GsAElHi SA G SF B AS=!:
GsAElHi SA G SF B AS=!:
m-e+-:-
m-e+-:-
These SRs apply to each Function in SUR VEILL ANCE REQUIREMENTS
These SRs apply to each Function in SURVEILLANCE REQUIREMENTS  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NO TE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
RefeF =!:s Table 3.3.5.2-1 =!:s Ele=!:eFffliAe WAiCA SRs apply fsF eacFI EGGS F~Ac=!:isA .
RefeF =!:s Table 3.3.5.2-1 =!:s Ele=!:eFffliAe WAiCA SRs apply fsF eacFI EGGS F~Ac=!:isA SURVEI LLANC E SR 3.3.5.2. 1 Perform CHANN EL CHECK.
SURVEI LLANC E                                                                 FREQUENCY SR     3.3.5.2. 1             Perform CHANN EL CHE CK.                                                               I n accordance wi th the Surve i 11 ance Frequency Control Program SR     3.3.5.2.2             Perform CHANNE L FUNCTIONAL TEST.                                                       In accordance with the Surveil l ance Frequency Control Program LaSal l e 1 and 2                                                   3.3.5.2-2                                 Amendmen t No. 230/216
SR 3.3.5.2.2 Perform CHANNE L FUNCTIONAL TEST.
LaSal l e 1 and 2 3.3.5.2-2 FREQUENCY In accordance wi th the Survei 11 ance Frequency Control Program In accordance with the Surveil l ance Frequency Control Program Amendment No. 230/216
 
RPV Water Inventory Control Instrumentation +-
3. 3. 5. 2 Table 3.3.5. 2-1 (page 1 of 2)
+
RPV Water Inve ntory Control Instrume ntatio n


RPV Water I nventor y Control I ns trumentation + -
========
                                                                                                                                  +
FUNCTION h
3 . 3 . 5. 2 Table 3. 3. 5. 2- 1 (page 1 of 2)
Le.. PFessriFe Gee l aAt IAjeetieA A (LPG!)
RPV Water Inve nt ory Control Instrume nt atio n
aA8 Le.. PFessriFe GeFe S19Fa)
= = = = = = = =
( LPGSJ Sri13s; stems  
APP LI CABLE                  G8Pl8 IT I8N S MOD ES OR      REQU IR ED    REFERDIGEB OTHER        CHANNE LS          -F-R8!4 SPECIFIED          PER        RE81:1 I RE8    Sl:IRVEI LLMIGE          AL LOWABLE FUNCTION                    CO NDIT IONS    FUNCTION     AGTI8PI A. l      RE81:1 I REMUITS        VAL UE h   Le .. PFessriFe Gee l aAt IAjeetieA A (LPG!)
..r.-
aA8 Le .. PFessriFe GeFe S19Fa) ( LPGSJ Sri13s; stems
ReaeteF Steam Beme PFessriFe Le..
      ..r.- ReaeteF Steam                                                             .&#xa3;tf    3. 3. 5. 2. 2 ~ ~
Beme PFessriFe Le ..
(!Ajeeti BA PeFmissi oe)
(!Ajeeti BA PeFmissi oe)
      -&-:-  LPGS Prim19                     ~             ~                          .&#xa3;tf    3 .3. 5. 2. 2 ~        &sect;I'm a AS Bi sei'1aF&sect;Je                                 ~..+                                              < 1835 &sect;J l3m Fle .. Le .. (B;13ass)
APP LI CABLE MOD ES OR OTHER SPECIFIED CO NDIT IONS LPGS Prim19  
      --:-  LPGI Prim13 A                   ~             ~                          .&#xa3;tf    3 .3. 5. 2. 2 ~ &sect;Jl3m a AS Bi sei'1aF&sect;Je                                 ~..+                                              < 2111 &sect;I'm Fl s .. Ls .. (B) 13a ss l 4-:-   LPGS aA8 LPGI ,',               ~              ~                          .&#xa3;tf    3 .3. 5. 2. 2 ~~
~
lAjeetieA LiAe                               ~..+
Bi sei'1aF&sect;Je Fle.. Le.. (B;13ass)
PFessriFe Ls ..
LPGI Prim13 A  
(lAjeetieA PeFmissioe)
~
  ~   LPGI B aA8 LPGI G Sri8s) stems
Bi sei'1aF&sect;Je Fl s.. Ls.. (B) 13a ss l 4-:-
      ..r.- ReaeteF Steam                                                             .&#xa3;tf   3. 3. 5. 2. 2 ~ ~
LPGS aA8 LPGI,',  
Bsme PFessriFe Ls ..
~
(lAjeetieA PeFmissi.el
lAjeetieA LiAe PFessriFe Ls..
      -&-:-  LPG! Prim13 B                                                              .&#xa3;tf   3.3. 5.2.2     ~       &sect;Jl3m aAS aA8 LPGI Prim13 G                                                                                < 2111 &sect;I'm Bisei'1aF&sect;Je Fle .. Le .. (B)13ass)
(lAjeetieA PeFmissioe)  
      --:-  LPG! B aA8 LPG! G                                                          .&#xa3;tf   3.3. 5.2.2     ~ ~
~ LPGI B aA8 LPGI G Sri8s) stems  
lAjeetisA LiAe PFessriFe Le ..
..r.-
(lAjeetieA PeFmissi.el (contin ued)
ReaeteF Steam Bsme PFessriFe Ls..
+a-+ Asseeiates .. itR aA EGGS sril3s;stem FeEfriiFe8 te 13e 8PERABLE 13; LG8 3 . 5 . 2 , " RPV ', /ateF !AoeAtef)
(lAjeetieA PeFmissi.el LPG! Prim13 B aA8 LPGI Prim13 G Bisei'1aF&sect;Je Fle.. Le.. (B)13ass)
GeAtFel . "
LPG! B aA8 LPG! G lAjeetisA LiAe PFessriFe Le..
LaSal l e 1 and 2                                         3 . 3 .5.2-3                         Amendmen t No. 230/216
(lAjeetieA PeFmissi.el REQU IR ED CHANNE LS PER FUNCTION
~
~..+
~
~..+
~
~..+
G8Pl8 IT I8N S REFERDIGEB
-F-R8!4 RE81:1 I RE8 AGTI8PI A. l Sl:IRVEI LLMIGE RE81:1 I REMUITS AL LOWABLE VALUE
.&#xa3;tf 3. 3. 5. 2. 2 ~  
~  
.&#xa3;tf 3. 3. 5. 2. 2 ~
&sect;I'm a AS
< 1835 &sect;J l3m
.&#xa3;tf 3. 3. 5. 2. 2  
~  
&sect;Jl3m a AS
< 2111 &sect;I'm  
.&#xa3;tf 3. 3. 5. 2. 2 ~~
.&#xa3;tf 3. 3. 5. 2. 2  
~  
~  
.&#xa3;tf 3. 3. 5. 2. 2
~
&sect;Jl3m aAS
< 2111 &sect;I'm
.&#xa3;tf 3. 3. 5. 2. 2
~
~
(contin ued)  
+a-+ Asseeiates.. itR aA EGGS sril3s;stem FeEfriiFe8 te 13e 8PERABLE 13; LG8 3. 5. 2, " RPV ',/ateF !AoeAtef)
GeAtFel. "
LaSal l e 1 and 2 3. 3.5.2-3 Amendmen t No. 230/216  


RPV Water In ventory Control                In strumentation ~
3.3 .5 .2 Table 3 . 3.5.2-1 (page 2 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE                    co~rn  IT ID~Js MODES OR          REQUIRED    REFERDJCEB OTHER          CHANNELS        -F-OOM SPECIFIED            PER      REGl:IIREB      Sl:IRVEI LLMICE          ALLOWAB LE FUNCTION                CONDITIONS        FUNCTION    ACTION A. 1      RE81:1IREMEMTS              VALUE
:-  Iii &sect;A PFesstJFe Cs Fe S13Fa) ( llPCSl S)steFA 13-7  l l PGS PtlFA/3                                                        ~    3. 3. 5. 2. 2      > 113 . 2 13si&sect; Bi seAaF&sect;e PFeSStJFe Iii &sect;A rnnass)
            -&-:- l l PCS S) steFA Fl e"                                                  ~    3. 3 . 5. 2. 2    ~~
Rate Le .. (8)13ass)                                                                            -a-A4
                                                                                                                  <  219~  &sect;/3FA
[]
[]
~   4-:-   RHR Shutdown Coo li ng Syste m Isolation
FUNCTION :-
: a. Reactor Vessel               ( !> )
Iii &sect;A PFesstJFe Cs Fe S13Fa)
2 in one                   ~     3. 3. 5. 2. 1    ;:: 11. 0 Water Leve l - Low,                          trip                      ~     3. 3. 5. 2. 2     inches Level 3                                      system
( llPCSl S)steFA 13-7 ll PGS PtlFA/3 Bi seAaF&sect;e PFeSStJFe Iii &sect;A rnnass) llPCS S) steFA Fl e" Rate Le.. (8)13ass)
~,,.,.       Reoctoc Wotec Cleooop (RWC UJ System I solation
~
: a. Reactor Vessel
4-:-
                                          ~   ( !> )
RHR Shutdown Cooli ng System Isolation a. Reactor Vessel Water Leve l -Low, Level 3
2 in one                    ~     3.3. 5.2.2       ;:: - 58. 0 Water Leve l - Low                            trip                                              inches Low, Level 2                                system
~,,.,. Reoctoc Wotec Cleooop (RWCUJ System Isolation a. Reactor Vessel Water Leve l - Low Low, Level 2 RPV Water In ventory Control In strumentation ~
  +a-+   AssseiateEI .. itfl aA EGGS StlBS)SteFA FetjtJiFeE1 ts 13e OPE 11ABL E B) LCO 3 . 5 . 2 , " IWV '.later lAoeAtSF)
3.3.5.2 Table 3.3.5.2-1 (page 2 of 2)
CsAtFe l ."
RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS
~)       When automatic isolation of the associated penetration f l ow path(s) i s credited in calculat in g DRAIN TIME.
( !> )  
LaSal le 1 and 2                                           3.3.5.2-4                         Amendmen t       No. 230 / 2 16
~
( !> )
REQUIRED CHANNELS PER FUNCTION 2 in one trip system 2 in one trip system co~rn IT ID~Js REFERDJCEB
-F-OOM REGl:IIREB ACTION A. 1 Sl:IRVEI LLMICE RE81:1IREMEMTS
~ 3. 3. 5. 2. 2
~ 3. 3. 5. 2. 2  
~ 3. 3. 5. 2. 1
~ 3. 3. 5. 2. 2
~ 3. 3. 5. 2. 2 ALLOWAB LE VALUE
> 113. 2 13si&sect;
~~
-a-A4 219~ &sect;/3FA
;:: 11. 0 inches
;:: - 58. 0 inches  
+a-+
AssseiateEI.. itfl aA EGGS StlBS)SteFA FetjtJiFeE1 ts 13e OPE 11ABLE B) LCO 3. 5. 2, " IWV '.later lAoeAtSF)
CsAtFe l."  
~)
When automatic isolation of the associated penetration f l ow path(s) i s credited in calculatin g DRAIN TIME.
LaSal le 1 and 2 3.3.5.2-4 Amendmen t No. 230 / 216


Prima ry Containment I sol ation In strumentation 3 . 3 .6.1 ACT IO NS CON DIT ION                                                       REQUIRED ACT IO N                                    CO MPL ET IO N TI ME J.       As requ i red by Re qui re d                              J .l                Init i ate action to                              Immed i at el y Act i on C.l and referenced                                                   restore cha nne l to i n Ta bl e 3. 3. 6.1-1.                                                     OP ERAB LE st at us .
ACT IONS CON DIT ION J.
I Ait i ate aetieA ts                             IF!HtteEl i a te l )
As requ i red by Re qui red Act i on C.l and referenced i n Ta bl e 3.3.6.1-1.
i se l ate Hie Resi E1 1:1a l li e at Remeva l (R llR ) Sl91:1 tE1e .. A Cee li A&sect; (S BC) S)ste m.
SURVEI LLANCE REQU I RE ME NTS J.l Primary Containment Isol ation In strumentation 3. 3.6.1 REQUIRED ACT ION Init i ate action to restore cha nne l to OP ERAB LE st at us.
SURVEI LLANCE REQU I RE ME NTS
IAit i ate aetieA ts i se l ate Hie Resi E1 1:1a l li e at Remeva l (R llR ) Sl91:1 tE1e.. A Cee li A&sect; (S BC) S)ste m.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOT ES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
COMPL ET IO N TI ME Immed i at ely IF!HtteEl i a te l )
: 1.       Refer to Tab l e 3 . 3.6 . 1- 1 to deter mi ne whi ch SRs ap pl y for eac h Pr imary Contai nme nt Isolat i on Fu nction.
- - - - --- -- - -- --- -- -- - -- - -- -- - - -- -- -- - -- - -- -- - NOT ES -- -- -- - --- -- - -- --- -- -- - -- - -- --- -- --- --- - - -
: 2.       Whe n a chan nel is pl aced in an i noperable sta t us so l ely for pe r for mance of requi red Survei l lances , entry in to assoc i ate d Con diti ons and Re qui re d Ac ti ons may be de l ayed f or up to 6 hour s provi ded t he assoc i at ed Fun ct i on mainta i ns isolation capa bi l i ty .
: 1.
SURVEI LLANCE                                                                               FR EQ UEN CY SR     3. 3.6 . 1. 1                   Perfor m CHANNEL CHE CK .                                                                         I n accorda nce wit h t he Sur veil l ance Freq uency Co ntrol Progra m
Refer to Tab l e 3.3.6.1-1 to determi ne whi ch SRs ap pl y for eac h Primary Contai nme nt Isolat i on Function.
                                                                                                                                                                                  +
: 2.
SR     3. 3.6 . 1.2                   Perfor m CHANNEL FUN CTIO NAL TES T.                                                               In accordance wit h th e Survei l lance Fre que ncy Con t ro l Program (cont i nued)
Whe n a chan nel is pl aced in an i noperable sta t us so l ely for pe rfor mance of requi red Survei l lances, entry into assoc i ated Conditi ons and Requi re d Acti ons may be de l ayed f or up to 6 hours provi ded t he assoc i at ed Funct i on mainta i ns isolation capa bi l i ty.
LaSalle 1 and 2                                                                  3 . 3 .6.1-4                                    Amendment No. 200 / 187
SURVEI LLANCE SR 3.3.6.1. 1 Perform CHANNEL CHE CK.
SR 3.3.6.1.2 Perform CHANNEL FUN CTIONAL TEST.
LaSalle 1 and 2 3. 3.6.1-4 FR EQ UEN CY In accorda nce wit h t he Sur veil l ance Frequency Co ntrol Program In accordance wit h the Survei l lance Freque ncy Con t ro l Program (cont i nued)
Amendment No. 200/ 187  
+


LOP Instrumentation 3.3.8.1 3.3      INSTRUMENTATION 3.3.8.1           Loss of Power (LOP) Instrumentation LCO     3.3.8.1                 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
3.3 INSTRUMENTATION LOP Instrumentation 3.3.8.1 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
APPLICABILITY:                   MODES 1, 2, and 3...,                 ~
APPLICABILITY:
                                  '1Jf1eA Hie associatee eiese l &sect;eAerator (DC) is re~uiree to be OP CRABLE by LCO 3. 8 . 2, "AG Sources Sl'l uteo *,m ."
ACTIONS MODES 1,  
ACTIONS
'1Jf1eA Hie OP CRABLE 2, and 3..., ~
associatee eiese l &sect;eAerator (DC) is re~uiree to be by LCO 3.8. 2, "AG Sources Sl'l uteo*,m."  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is all owed for each channel.
Separate Condition entry is all owed for each channel.
CONDITION                                             REQUIRED ACTION                             COMPLETION TIME A.     One or more channels                           A.1             Place channe l in                         1 hour inoperable.                                                     trip.
CONDITION REQUIRED ACTION COMPLETION TIME A.
B.     Required Action and                             B.1             Declare associated DG                     Immediately associated Completion                                           inoperable.
One or more channels A.1 Place channe l in 1 hour inoperable.
trip.
B.
Required Action and B.1 Declare associated DG Immediately associated Completion inoperable.
Time not met.
Time not met.
LaSalle 1 and 2                                                     3.3.8.1-1                               Amendment No. H 7/133
LaSalle 1 and 2 3.3.8.1-1 Amendment No. H 7/133  


ECCS-Operating
ECCS-Operating
: 3. 5. 1 3.5       EMERGENCY CORE COOLING SYSTEMS CECCS), REACTOR PRESSURE VESSEL CRPV)
: 3. 5. 1 3.5 EMERGENCY CORE COOLING SYSTEMS CECCS), REACTOR PRESSURE VESSEL CRPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING CRCIC)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING CRCIC)
SYSTEM 3.5.1         ECCS-Operating LCO     3.5.1                   Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
APPLICABILITY:                   MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure ~ 150 psig.
APPLICABILITY:
High Pressure Core Spray (HPCS)
MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure ~ 150 psig.
ACTIONS
ACTIONS High Pressure Core Spray (HPCS)  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
LCO 3.0.4.b is not applicable to H-P-G-& .
LCO 3.0.4.b is not applicable to H-P-G-&.
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 A.
(continued)
One low pressure ECCS injection/spray subsystem inoperable.
LaSalle 1 and 2                                                        3.5.1-1                                 Amendment No. 230 / 216
LaSalle 1 and 2 A. 1 REQUIRED ACTION COMPLETION TIME Restore low pressure 7 days ECCS injection/spray subsystem to OPERABLE status.
(continued) 3.5.1-1 Amendment No. 230/ 216  


ECCS-Operating
ACTIONS CONDITION B.
: 3. 5. 1 ACTIONS CONDITION           REQUIRED ACTION          COMPLETION TIME B. l ligfi PresstH' e Core B.1  Verify by              Immediately S~ray   ( HPCS+ System       administrative means inoperable.                   RCIC System is OPERABLE when RCIC is required to be OPERABLE.
lligfi PresstH' e Core S~ray (HPCS+ System inoperable.
B.2   Restore HPCS System    14 days to OPERABLE status.
B.1 B.2 C.
C. Two low pressure ECCS   C.1   Restore one low        72 hours injection/spray               pressure ECCS subsystems inoperable.        injection/spray subsystem to OPERABLE status.
Two low pressure ECCS C.1 injection/spray subsystems inoperable.
D. Required Action and     D.1  Be in MODE 3.          12 hours associated Completion Time of Condition A, B, or C not met.
D.
E. One required ADS valve E.1   Restore required ADS    14 days inoperable.                  valve to OPERABLE status.
Required Action and associated Completion Time of Condition A, B, or C not met.
F. Required Action and     F.1  Be in MODE 3.          12 hours associated Completion Time of Condition E not met.
D.1 E.
(continued)
One required ADS valve E.1 inoperable.
LaSalle 1 and 2                 3.5.1-2               Amendment No. 196/183
F.
Required Action and associated Completion Time of Condition E not met.
LaSalle 1 and 2 F.1 REQUIRED ACTION ECCS-Operating
: 3. 5. 1 COMPLETION TIME Verify by Immediately administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.
Restore HPCS System to OPERABLE status.
14 days Restore one low 72 hours pressure ECCS injection/spray subsystem to OPERABLE status.
Be in MODE 3.
Restore required ADS valve to OPERABLE status.
Be in MODE 3.
12 hours 14 days 12 hours (continued) 3.5.1-2 Amendment No. 196/183  


RPV Water Inventory Control .+----
RPV Water Inventory Control.+----
: 3. 5. 2 ACTIONS (continued)
: 3. 5. 2 ACTIONS (continued)
I
-----------.-----------.---------~
-----------.-----------.---------~
                                                                            - I 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 C.
C.2  Verify each secondary   4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
DRAIN TIME < 36 hours and
                                                        -i(SGT)I C.3  Verify one sta   y     4 hours gas treatment /
~ 8 hours.
subsystem is capable of being placed in operation in less than the DRAIN TIME.
LaSalle 1 and 2 C.1 C.2 C.3 REQUIRED ACTION Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.
(continued)
COMPLETION TIME 4 hours Verify each secondary 4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.  
LaSalle 1 and 2                3.5.2-2               Amendment No. 230 / 216
/
-i(SGT)I Verify one sta y
4 hours gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
(continued) 3.5.2-2 Amendment No. 230/ 216  


RPV Water In ventory Control ..+--
ACTION S (continued)
3 .5 .2 AC TION S  (continued)
COND ITION D.
COND ITION                    REQUIRED AC TION                       COMP LETION TIME D. DRAIN TIME    < 8 hours. D.1      - - - - - - -NOTE- - - - - - - -
DRAIN TIME < 8 hours.
Required ECCS injection/spray subsystem or additional method of water injection sh a 11 be capab le of operating without off site electrical power.
D.1 AND D.2 AND D. 3 RPV Water In ventory Control..+--
Initiate action to                   Immediately establish an additional method of water inj ect i on wit h water sources capab l e of maintaining RPV water l eve l > TAF for
3.5.2 REQUIRED AC TION COMP LETION TIME  
: '.'. 36 hours .
- -- - - - -NOTE- - - - - - - -
AND D.2      Initi ate action to                 Immediately establish secondary conta inment boundary.
Required ECCS injection/spray subsystem or additional method of water injection sh a 11 be capable of operating without off site electrical power.
AND D. 3    Initiate action to                   Immediately isolate each
Initiate action to Immediately establish an additional method of water inj ect i on wit h water sources capab l e of maintaining RPV water l eve l > TAF for
!automatically or    }-----____                   secondary containment
::'.'. 36 hours.
                              ---------            penetration flow path r---__ , or verify it can be I     ~ manually isolated from the control room.
Initi ate action to Immediately establish secondary conta inment boundary.
D.4      Initi ate     a~
Initiate action to Immediately isolate each  
verify one staA~~Y Immediately
}-----____
                                                  &sect;as treatmCAt subsystem is capable of being placed in operat i on.
secondary containment penetration flow path  
(cont in ued)
!automatically or LaSal le 1 and 2 r---__, or verify it can be I  
LaSal le 1 and 2                          3.5.2 -3                           Amendmen t No. 230/216
~ manually isolated D.4 from the control room.
Initi ate a~
verify one staA~~Y  
&sect;as treatmCAt subsystem is capable of being placed in operat i on.
Immediately (cont in ued) 3.5.2 -3 Amendment No. 230/216  


NOTES
NOTES
: 1. Operation may be through the test return line.
: 1. Operation may be through the test return line.
: 2. Credit may be taken for normal system                                                       RPV Water In ventory Control operation to satisfy this SR.                                                                                                     3 .5 .2 SURV EILL ANC E 0 EQUIREMENTS            (cont inu ed)
: 2. Credit may be taken for normal system RPV Water In ventory Control operation to satisfy this SR.
SURVE ILLANC E                                                         FREQUEN CY
3.5.2 SURV EILLANC E 0EQUIREMENTS (cont inued)
          -&ff 3. 5. 2. 5                                         -
SURVE ILLANC E FREQUEN CY  
                                                                    '"ITC
-&ff 3. 5. 2. 5  
                                                                        ~
'"ITC  
                                                                                                                                        -I---
~  
p~ 8t PeEjtd PeEI t8 ee lflet f e P S:'J'Stelfl ~'eAt f 1 8111' i:iaHis ei:ieAeEI l::!ASeP aEllfli Ai s=l:Pa=t i 'i'e eeA=l:Pe i .
-I---
                              \I e Pi f:,' , feP He PeEj l: ! i PeEI EGGS i Aj ee=t i 8A1'SFJPa:'7' Sl::!B5:'7'5 t elfl , eae A lfla Al::!a 1 ,
p~ 8t PeEjtd PeEI t8 ee lflet f e P S:'J'Stelfl  
i:ie 1~e P ei:iePa=te EI , a AEI al: ! te lfl a=tie 1 ~a 1 1 ~e i A He 1
~'eAt f 1 8111' i:iaHis ei:ieAeEI l::!ASeP aEllfli Ai s=l:Pa=t i 'i'e eeA=l:Pe i.  
f 1 8~1 13aH , Hat i 5 Aet iee l<eEI , sea i eEI , 8P
\\I e Pi f:,', feP He PeEj l::! i PeEI EGGS  
                                                                                                                +/-A aeeePdaAee 11~i tAHe Sl::!P~' ei 11 aAee
+/-A aeeePdaAee i Aj ee=t i 8A1'SFJPa:'7' Sl::!B5:'7'5 t elfl, eae A lfla A l::!a 1,
                                                                                                                ~PeEfl::!eAE :'7'
11~i t A H e
                                                                                                                                        +-
+-
eHe P~vi se seel::!PeEI i A 13 es i tieA , i 5 i A He                           Ge At Pei PPe&sect;Palfl eeP Peet i:iesitieA .
i:ie 11~e P ei:iePa=te EI, a AEI a l::!te lfla=tie 1~a 1 1~e i A He Sl::!P~' ei 11 aAee f 1 8~1 13aH, Hat i 5 Aet iee l<eEI, sea i eEI, 8P  
t
~PeEfl::!eAE :'7' eHe P~vi se seel::!PeEI i A 13es i tieA, i 5 i A He Ge At Pei PPe&sect;Palfl eeP Peet i:iesitieA.  
                            ~
~
SR   3.5.2. Operate the required ECCS i njection/spray                                       In accordance subsys tem through the reci rcul ati on lin e for                               with the
SR 3.5.2. Operate the required ECCS i njection/spray In accordance  
                        ~
~
                              ~ 10 minutes.                                                                     Survei 11 ance Frequ ency Control Program SR   3 . 5.2 . Verify each valve credited for automatically                                     In accordance isolating a penetration fl ow path actuates                                     with the
subsys tem through the reci rcul ati on lin e for with the  
                        ~    to the isolation position on an actual or s imulat ed i so l at i on s ig nal.
~ 10 minutes.
Survei 11 ance Frequ ency Control Program SR   3.5.2 . .g   - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - -
Survei 11 ance Frequ ency Control Program t SR 3. 5.2. Verify each valve credited for automatically In accordance  
~
isolating a penetration fl ow path actuates with the to the isolation position on an actual or Survei 11 ance simulated i so l at i on signal.
Frequ ency Control Program SR 3.5.2..g  
- - - - - - - - - - - - - - - - - - -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.
Verify the required ECCS injection/spray                                         In accordance s ubsystem can be manually operated.                                             with the Survei 11 ance Frequency Control Program LaSal le 1 and 2                                         3.5.2 -5                             Amendmen t No. 23 0/2 16
with the Survei 11 ance Frequency Control Program LaSal le 1 and 2 3.5.2 -5 Amendment No. 230/2 16  


AC Sources-Shutdown 3.8.2 ACTIONS CONDITION                                      REQUIRED ACTION                              COMPLETION TIME D. Required offsite                       D.1          Declare associated                          Immediately circuit or DG of LCO                                 standby gas treatment Item d. inoperable.                                   subsystem, control room area filtration subsystem, and control room area ventilation air conditioning subsystem inoperable.
ACTIONS CONDITION REQUIRED ACTION AC Sources-Shutdown 3.8.2 COMPLETION TIME D.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                            FREQUENCY SR 3.8.2.1       - - - - - - - - - - - - - - - - - - -NOTE-& - - - - - - - - - - - - - - - - - - -
Required offsite circuit or DG of LCO Item d. inoperable.
                        +.:-       The following SRs are not required to                                       , SR 3.8.1.10, be performed: SR 3.8.1.3, SR 3.8.1.9                                         SR 3.8.1.14, and tAFS~&sect;A SR 3 . 8 . 1 . 11 , SR 3 . 8 . 1 . 13 tAFS~&sect;A SR 3.8.1.16, SR 3 . 8 . 1 . 18 , UftE!.
D.1 Declare associated Immediately standby gas treatment subsystem, control room area filtration subsystem, and control room area ventilation air conditioning subsystem inoperable.
SR 3 . 8 . 1. 19 .
SURVEILLANCE REQUIREMENTS SR 3.8.2.1 The following SRs are applicable for SURVEILLANCE
                        ~         SR 3 . 8 . 1 . 12 aA8 SR 3 . 8 . 1 . 19 are As t Fe ~~i Fe G te Be ffi et .
- - - - - - - - - - - - - - - - - - -NOTE-&- - - - - - - - - - - - - - - - - - -
The following SRs        f.&r AC sources required to be OPERABLE,                                             In accordance are applicable for        SRs ef S13ee if ieatieA 3 . 8 . l , eJ(eqit                                         with applicable SR 3 . 8 . 1 . 8 , SR 3 . 8 . 1 . 17 , aA8 SR 3 . 8 . 1 . 20 ,                       SRs a Fe a1313l i casl e .
+.:-
SR 3.8.1.1                     SR   3.8.1 .6 SR 3.8.1.2                      SR   3.8.1 .9 SR 3.8.1.3                     SR   3.8.1 .10 SR 3.8.1.4                      SR   3.8.1 .14 SR 3.8.1.5                      SR   3.8.1 .16 LaSalle 1 and 2                                           3.8.2-4                               Amendment No. 230 / 216
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.9 tAFS~&sect;A SR 3.8. 1. 11, SR 3.8. 1. 13 tAFS~&sect;A SR 3.8.1.16, SR 3.8. 1. 18, UftE!.
SR 3.8. 1. 19.  
~ SR 3.8. 1. 12 aA8 SR 3. 8. 1. 19 are As t Fe ~~i Fe G te Be ffiet.
f.&r AC sources required to be OPERABLE, SRs ef S13ee if ieatieA 3.8. l, eJ(eqit SR 3.8. 1. 8, SR 3.8. 1. 17, aA8 SR 3.8. 1. 20,
a Fe a1313l i casl e.
SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.9 SR 3.8.1.10 SR 3.8.1.14 SR 3.8.1.16 FREQUENCY
, SR 3.8.1.10, SR 3.8.1.14, and In accordance with applicable SRs LaSalle 1 and 2 3.8.2-4 Amendment No. 230 / 216  


ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.5.2-2 3.5.2-4 3.5.2-5 3.5.2-6 3.6.1.3-1 3.6.1.3-4 3.8.2-5
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.5.2-2 3.5.2-4 3.5.2-5 3.5.2-6 3.6.1.3-1 3.6.1.3-4 3.8.2-5  


Definitions
Definitions
: 1. 1 1.1 Definitions     (continued)
: 1. 1 1.1 Definitions (continued)
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 i s the larger of the drain rate through a s ingle 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 eveRt ,
The water inventory above the TAF is divided by the limiting drain rate;
l oss of Rormeil poi,ier , siRgle hblmeiR error) ,
: b.
The limiting drain rate i s 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 eveRt,
l oss of Rormeil poi,ier, siRgle hblmeiR error),
for all penetration flow paths below the TAF except:
for all penetration flow paths below the TAF except:
: 1. Penetration flow paths connected to an intact closed system, or i so lated by closed and administratively controlled        manual or automat ic va l ves that are l ockeEi , seei l eEi , or otheni'i se secblreEi in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
closed and administratively controlled
: 2. Penetration flow paths capab le of being isolated by valves that wi ll close automatically with out offsite power prior to the RPV water le vel being equal to the TAF when actuated by RPV water le ve l isolation instrumentation; or
: 1.
: 3. Penetration flow paths with is olation 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 commun ication with the control room, i s stat ioned at the controls, and is capable of closing the penetration flow path i solat ion device without offsite power.
Penetration flow paths connected to an intact closed system, or i so lated by manual or automat ic va l ves that are Quad Cities 1 and 2 l ockeEi, seei l eEi, or otheni'i se secblreEi 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 wi ll close automatically with out offsite power prior to the RPV water le vel being equal to the TAF when actuated by RPV water leve l 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 commun ication with the control room, i s stat ioned at the controls, and is capable of closing the penetration flow path i solat ion device without offsite power.
(continued)
(continued)
Quad Cities 1 and 2                        1. 1-4                     Amendment No. 279/274
: 1. 1-4 Amendment No. 279/274  


RPV Water I nventory Control I nstrumentation 3.3 . 5.2 3.3        I NS TRUMENTATI ON 3 . 3 . 5.2       Reactor Pressure Vesse l (RPV) Water I nventory Contro l I nstrumentat i on LCO       3.3.5.2                 The RPV Water Inventory Contro l instrumentat i on for each Funct i on in Table 3.3.5.2 - 1 shal l be OPERAB LE.
3. 3 I NSTRUMENTATI ON RPV Water Inventory Control Instrumentation 3.3. 5.2 3. 3. 5.2 Reactor Pressure Vesse l (RPV) Water Inventory Contro l Instrumentat i on LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentat i on for each Funct i on in Table 3.3.5.2 -1 shal l be OPERAB LE.
AP PLI CAB ILIT Y:               According to Tab l e 3.3.5.2- 1 .
AP PLI CAB ILITY:
ACTIONS
According to Tab l e 3.3.5.2-1.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NO TE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
ACTIONS  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Cond i tion entry is al lowed for each channel.
Separate Cond i tion entry is al lowed for each channel.
A.1 Initiate action to place channel in trip CON DIT ION                                       OR                                               COMP LETI ON TI ME
A.1 Initiate action to place channel in trip CON DIT ION OR COMP LETI ON TI ME  
  /Jr.. 0Ae 8P lfl8Pe cl9aAAel s                       A-:-           EA:f:et" =E 19 e CeAE1it:ieA               IlfllfleE1i at: el y i Ae13 n a 131 e .                                             PefereAceE1 i A A. One or more                                                Tas le 3 . 3 . 5. 2 1 fep                   rllmmediately             I r     channels inoperable.
/Jr..
                                                          .J He el9aAAel .
0Ae 8P lfl8Pe cl9aAAel s A-:-
JV                                                      '4 B-:-   As PeEjui PeE1 B:Y                             &#xa3;-:-+           Dec l are assoc i ated                     Immediate l y ReEjui PeE1 ,01c=EieA A . 1                                   penetration fl ow a As Pe:fePeAces i A I A~.11          path(s) incapable of c
EA:f:et"  
Ta sle 3 . 3 . 5. 2 1.                                         automatic isolation.
=E 19 e CeAE1it:ieA IlfllfleE1i at: el y i Ae13 n a 131 e.
                                                        ~               f   Initiate action to calculate IA.2.2     H     ~ -B-ti-         Cal cul a=Ee DRA I N TI ME.                 Immed i ate l y
PefereAceE1 i A Tas le 3. 3. 5. 2 1 fep rllmmediately I A. One or more He el9aAAel.
: c. As PeEjUi PCS             B)'                       -:-+       Place CAaAAel i A fPij3 .                     1   A8UP ReEjUiPeS Ac=EieA A. 1 a AE1 PefePeAeeE1 i A
r channels inoperable.  
:i:a 81 e 3 . 3 . 5 . 2 1.
.J JV
D. As PeEjUi PeE1 B)'                               ~           Resf:epe el9aAAel f; 0                         2q A8UPS ReEjuiPe8 Act:ieA A. 1                                         OPERABLE st:a t:us .
'4 B-:-
a AE1 PefePeAeeE1 i A Tasle 3 . 3 . 5 . 2 1.
As PeEjui PeE1 B:Y  
(continued)           I Quad Ci t i es 1 and 2                                               3.3.5.2-1                               Amendment No. 273/268
&#xa3;-:-+
Dec l are assoc i ated Immediate l y ReEjui PeE1,01c=EieA A. 1 IA~.11 penetration fl ow a As Pe:fePeAces i A path(s) incapable of Ta sle 3.3. 5. 2 1.
automatic isolation.
c ~
f Initiate action to calculate IA.2.2 H ~ -B-ti-Cal cul a=Ee DRA IN TI ME.
Immed i ate l y
: c. As PeEjUi PCS B)'  
-:-+
Place CAaAAel i A fPij3.
1 A8UP ReEjUiPeS Ac=EieA A. 1 a A E1 PefePeAeeE1 i A
:i:a 81 e 3.3. 5. 2 1.
D. As PeEjUi PeE1 B)'  
~ Resf:epe el9aAAel f; 0 2q A8UPS ReEjuiPe8 Act:ieA A. 1 OPERABLE st:a t:us.
a AE1 PefePeAeeE1 i A Tasle 3.3. 5. 2 1.
(continued) I Quad Ci t i es 1 and 2 3.3.5.2-1 Amendment No. 273/268  


RPV Water I nventory Control I nstrumentation 3.3 . 5.2 ACTIONS COND IT ION                                          REQUI RED ACTION                             COM PLE TI ON TIM E E. ReEjtl i FEEi Aet i sA a AEl                        f-:4.       Deel a Fe assseiateEI l S\i'                 l A'IA'leEl i a tel y                 J assseiateEI GSA'if3 l et i SA                                 f3FESSl:lFe EGGS                                                               /
ACTIONS COND IT ION RPV Water Inventory Control Instrumentation 3.3. 5.2 REQUI RED ACTION COM PLETI ON TIM E  
f i ffie Sf GsAElitisA G SF                                   i Ajeeti SA 11 s13 Fa:,*
- J E. ReEjtl i FEEi Aet i sA a A El f-:4.
D ASt ffiet .                                                 StlBS:)'Steffi i As13eFa l=Jl e .
Deel a Fe assseiateEI l S\\i' l A'IA'leEl i a tel y assseiateEI GSA'if3 l et i SA f3FESSl:lFe EGGS  
rJThese SRs apply to each Function in I
/
SURV EILL ANC E REQ UIR EMENTS
f i ffie Sf GsAElitisA G SF i Ajeeti SA11s13 Fa:,*
                                                                                                                                                          -)
D A St ffiet.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
StlBS:)'Steffi i As13eFa l=Jl e.
~ ef:eF ts Tab l e 3.3.5.2-1 ts EleteFA'liAe ld ~i e~ SRs a1313 l y f:sF eae~ EGGS FtlAetisA .
rJThese SRs apply to each Function in I SURV EILLANC E REQ UIREMENTS
SURV EI LLANC E                                                               FREQU ENCY I
-)  
SR     3.3.5 . 2 . 1             Perform CHANNE L CHECK .                                                         In accordance with the Surve i 11ance
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
                                                                                                                                                          -)
~ ef:eF ts Tab l e 3.3.5.2-1 ts EleteFA'liAe ld ~i e~ SRs a1313 ly f:sF eae~ EGGS FtlAetisA.
Frequency Control Program                   ..
SURV EILLANC E FREQU ENCY I
SR     3.3.5.2 . 2               Perform CHANNEL FUNCTIONAL TE ST.                                                 In accordance with the Survei 11ance Frequency Control Program Quad Ci t i es 1 and 2                                               3.3.5.2-2                               Amendment No. 273/268
SR 3.3.5. 2. 1 Perform CHANNE L CHECK.
In accordance with the Surve i 11 ance Frequency
-)
Control Program..
SR 3.3.5.2. 2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Survei 11 ance Frequency Control Program Quad Ci t i es 1 and 2 3.3.5.2-2 Amendment No. 273/268  


RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3 . 3.5 . 2-1 (Page 1 of 1)
FUNCTION h
RPV Wat e r Inventory Control Instrumentatio n APPLICABLE                              G8~18 I TI 8N S MODES                                REFERUIGEB OR OTHER            REQU I RED            fiWM SPECIFIED        CHANNELS PER          RE88IRE9        S8R"EI LL ' NGE        ALLOWABLE FUNCTIO N                CONDITIONS          FUNCTIO N          AGT I 8N P . l    RE88IREMENTS              VAL UE h      Ge Fe S13Fa; S; stelll tt7   Reaete1- Stealll Bellle                                                                 5-lt  3. 3 . 5. 2. 2 P1 esst:H'e Le (Pe:lllissi.el tr. GeFe S13Fa) P~lllf3                                                                     5-lt  3. 3 . 5. 2. 2 Bi SEAaF&sect;e Fl e Ls (8)13assl b     Le .. P1 ess~1 e Geel a19t IAjeetieA (LPG!) S;stelll tt7   ReaeteF Stealll Bellle                                                                 5-lt  3. 3 . 5. 2. 2 PFess~Fe Le ..
Ge Fe S13Fa; S; stelll tt7 Reaete1-Stealll Bellle P1 esst:H'e Le (Pe:lllissi.el tr.
(PeFl!lissi el tr. Le Press~Fe GeelaAt                                 +--!7tt                            5-lt  3. 3 . 5. 2. 2 IAjeeti SA P~lllf3                               le e13 (al Bi SEAaF&sect;e Fl e Le (B;13assl RHR Shutdown Cooling System (SOC) Isolation
GeFe S13Fa)
: a. Reactor Vessel Water                                 per trip                           5-lt 3. 3 . 5. 2. 1 ~ 3. 8 inches Level-Low                                        system                              5-lt 3. 3 . 5. 2. 2
P~lllf3 Bi SEAaF&sect;e Fl e Ls (8)13assl b
~ 4..,. Reactor Water Cleanup (RWCUJ System Isolatio n i
Le.. P1 ess~1 e Geel a19t IAjeetieA (LPG!) S;stelll  
: a. Reactor Vessel Water                                per trip                            5-lt 3. 3 . 5. 2. l ~ 3. 8 inches Level-Low                                          system                              5-lt 3. 3 . 5. 2. 2
~
        ' sseeiateEI     itA aA EGGS s~BS)Stelll Fe~~i FEEi te se   8PER ' BLE B) LG8 3 . 5 . 2 , " RP " llateF IA eAtSF) GeAtFel . "
tt7 ReaeteF Stealll Bellle PFess~Fe Le..
When automatic isolation of the associated pene t ration flow path(s) is credited in calculating DRAIN TIME .
(PeFl!lissi el tr.
Quad Cities 1 and 2                                           3.3.5.2-3                                   Amendment No. 273 / 268
Le Press~Fe GeelaAt IAjeeti SA P~lllf3 Bi SEAaF&sect;e Fl e Le (B;13assl RHR Shutdown Cooling System (SOC) Isolation
: a. Reactor Vessel Water Level-Low 4..,.
Reactor Water Cleanup (RWCUJ System Isolation
: a.
Reactor Vessel Water Level-Low RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3. 3.5. 2-1 (Page 1 of 1)
RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQU IRED CHANNELS PER FUNCTION
+--!7tt le e13 (al per trip system per trip system G8~18 I TI 8N S REFERUIGEB fiWM RE88IRE9 S8R"EI LL ' NGE AGT I 8N P. l RE88IREMENTS 5-lt
: 3. 3. 5. 2. 2 5-lt
: 3. 3. 5. 2. 2 5-lt
: 3. 3. 5. 2. 2 5-lt
: 3. 3. 5. 2. 2 5-lt
: 3. 3. 5. 2. 1 5-lt
: 3. 3. 5. 2. 2 5-lt
: 3. 3. 5. 2. l 5-lt
: 3. 3. 5. 2. 2 ALLOWABLE VALUE
~ 3.8 inches
~ 3.8 inches
' sseeiateEI itA aA EGGS s~BS)Stelll Fe~~i FEEi te se 8PER ' BLE B) LG8 3. 5. 2, " RP" llateF IA eAtSF) GeAtFel. " i calculating DRAIN TIME.
When automatic isolation of the associated penet ration flow path(s) is credited in Quad Cities 1 and 2 3.3.5.2-3 Amendment No. 273/ 268  


LOP Instrumentation 3.3.8.1 3.3      INSTRUMENTATION 3.3.8.1           Loss of Power (LOP) Instrumentation LCO       3.3.8.1                 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LOP Instrumentation 3.3.8.1 LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.
APPLICABILITY:                   MODES 1, 2, and 3, WAeA tAe associated diesel geAerator is reqHired to be OPERABLE by LCO 3 . 8 . 2 , " AC SoHrces SAHtdmm ."
APPLICABILITY:
ACTIONS
ACTIONS MODES 1, 2, and 3, WAeA tAe associated diesel geAerator is reqHired to be OPERABLE by LCO 3.8. 2, " AC SoHrces SAHtdmm."  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is all owed for each channel.
Separate Condition entry is all owed for each channel.
CONDITION                                             REQUIRED ACTION                               COMPLETION TIME A.     One or more channels                           A.1             Place channel in                           1 hour inoperable.                                                     trip.
CONDITION REQUIRED ACTION COMPLETION TIME A.
B.     Required Action and                             B.1             Declare associated                         Immediately associated Completion                                           diesel generator (DG)
One or more channels A.1 Place channel in 1 hour inoperable.
Time not met.                                                   inoperable.
trip.
Quad Cities 1 and 2                                                 3.3.8.1-1                                 Amendment No. 199/195
B.
Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)
Time not met.
inoperable.
Quad Cities 1 and 2 3.3.8.1-1 Amendment No. 199/195  
 
ACTIONS CONDITION C.
DRAIN TIME < 36 hours and
~ 8 hours.
Quad Cities 1 and 2 C.1 C.2 C.3 RPV Water Inventory Control ~
3.5.2 REQUIRED ACTION Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.
COMPLETION TIME 4 hours Verify each secondary 4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
~(SGT) I Verify one sta /
4 hours gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
(continued) 3.5.2-2 Amendment No. 273 / 268


RPV Water Inventory Control ~
ACTIONS CONDITION D.
3.5.2 ACTIONS 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.
C.2  Verify each secondary  4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.        ~(SGT)  I C.3  Verify one sta /        4 hours gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
(continued)
(continued)
Quad Cities 1 and 2            3.5.2-2              Amendment No. 273 / 268
D.3 RPV Water Inventory Control t 3.5.2 REQUIRED ACTION COMPLETION TIME Immediately Initiate action to isolate each secondary containment penetration flow path or verify it can be  
 
!automatically or f-------~-' manually isolated D.4 E.
RPV Water Inventory Control       t 3.5.2 ACTIONS CONDITION                        REQUIRED ACTION               COMPLETION TIME D.  (continued)                D.3          Initiate action to           Immediately isolate each secondary containment penetration flow path or verify it can be
Required Action and E.l associated Completion Time of Condition C or D not met.
                !automatically or f-------~-' manually isolated from the control room.
DRAIN TIME < 1 hour.
D.4          Initiate action to           Immediately verify one st aA~~ Y ga s treatmeAt ~.L."::..---r1:SGT I subsystem is capable of being placed in operation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE from the control room.
E. Required Action and        E.l          Initiate action to           Immediately associated Completion                    restore DRAIN TIME to Time of Condition C or                  ~ 36 hours.
Initiate action to Immediately verify one st aA~~ Y ga s treatmeAt  
D not met.
~.L."::..---r1:SGT I subsystem is capable of being placed in operation.
DRAIN TIME  < 1 hour.
Initiate action to Immediately restore DRAIN TIME to  
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                          FREQUENCY SR 3.5.2.1     Verify DRAIN   TIME~     36 hours.                       In accordance with the Survei 11 ance Frequency Control Program (continued)
~ 36 hours.
Quad Cities 1 and 2                       3.5.2-4                     Amendment No. 273 / 268
FREQUENCY SR 3.5.2.1 Verify DRAIN TIME~ 36 hours.
In accordance with the Quad Cities 1 and 2 3.5.2-4 Survei 11 ance Frequency Control Program (continued)
Amendment No. 273/ 268  


RPV Water Inventory Control +-
RPV Water Inventory Control +-
: 3. 5. 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                    FREQUENCY SR   3.5.2.2       Verify, for the required ECCS injection/                                   In accordance spray subsystem, the:                                                     with the Survei 11 ance
: 3. 5. 2 SURVEILLANCE REQUIREMENTS SR 3.5.2.2 SR 3.5.2.3 -R 3
: a.       Suppression pool water level is                                 Frequency
. 5
                              ~   8.5 ft; or                                                   Control Program
. 2
: b.        Contaminated condensate storage tank(s) water volume is~ 140,000 available gallons.
~
SR  3.5.2.3      Verify, for the required ECCS                                             In accordance        'I' injection/spray subsystem, locations                                     with the susceptible to gas accumulation are                                       Survei 11 ance sufficiently filled with water.                                           Frequency Control Program
SURVEILLANCE Verify, for the required ECCS injection/
-R 3 . 5 . 2 . ~
spray subsystem, the:
Net l"etji:1i l"e E1 te s e FA et fel" sys t eFA 'o'eAt fl 8'oJ
: a.
                    ~a t ~ s   e ~ e A e E1 ~ A E1 el" aE1FAi Ai stPat i ve ceAtl"e l .
: b.
VeP ify , fe l"         t~ e     l"e ~~i l"e E1 EGGS                     IA acc e PE1aA ce
Suppression pool water level is  
                                                                                                                    +
~ 8.5 ft; or Contaminated condensate storage tank(s) water volume is~ 140,000 available gallons.
iAj ec tieA /s ~ P a y         s ~s sys t e fFI , eac~ FF1a A ~al ,      *,;i tA Hi e
Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
                    ~e 'oJCI"   e~el"ate E1 ,      aAE1 a~teFAat i c 'wa l ve iA Hie         S~l"vei ll aAce fl 8\1' ~atA ,       tAat is Aet l ecke E1 , sea l eE1 , el"             Fl"e~~eAcy et~el"wise         sec~PeE1 i A ~ esitieA , is iA t~e                     GeAtl"e l Pl"e &sect;l"aFA cel"l"ect      ~ esitieA .
Net l"etji:1i l"e E1 te se FAet fel" sys t eFA 'o'eAt fl 8'oJ  
(continued)
~a t ~ s e ~ e A e E1  
Quad Cities 1 and 2                                         3.5.2-5                       Amendment No. 273 / 268
~ A E1 el" aE1FAi Ai stPat i ve ceAtl"e l.
VeP ify, fe l" t~ e l"e ~~i l"e E1 EGGS iAj ec tieA /s ~ P a y s ~s sys t e fFI e a c ~
FF1a A ~al
~e 'oJCI" e~el"ate E1 aAE1 a~teFAat i c 'wa l ve iA Hie fl 8\\1' ~atA
, tAat is Aet l ecke E1, sea l eE1, el" et~el"wise sec~PeE1 i A ~ esitieA
, is iA t~e cel"l"ect
~ esitieA FREQUENCY In accordance with the Survei 11 ance Frequency Control Program In accordance
'I' with the Survei 11 ance Frequency Control Program
+
IA accePE1aA ce
*,;i tA Hi e S~l"vei ll aAce Fl"e~~eAcy GeAtl"e l Pl"e&sect;l"aFA (continued)
Quad Cities 1 and 2 3.5.2-5 Amendment No. 273/ 268  


NOTES
ISR 3.5.2.4 I
-&R-
: 3. 5. 2.5 NOTES
: 1. Operation may be through the test return line.
: 1. Operation may be through the test return line.
r In ventory Control 3 .5. 2
: 2. Credit may be taken for normal system I
                                                                                                                                              -r ISR 3.5.2.4 I                                2. Credit may be taken for normal system I     operation to satisfy this SR.
operation to satisfy this SR.
REQU I/REI I               SURVEI LLANCE                                                           FREQUENCY
REQU I/REI I
                                  'Y
SURVEI LLANCE  
              -&R- 3 . 5. 2. 5    Operate the required ECCS injection/spray                                           In accordance subsystem t A P S~&sect;A tA e Pec iP c ~latieA liA e                                   with the for ~ 10 minutes.                                                                   Survei 11 ance Frequency
'Y Operate the required ECCS injection/spray subsystem t A P S~&sect;A tA e Pec iP c ~latieA liA e for ~ 10 minutes.
~-                                                                                                                     Control Program SR 3.5.2.~----------------------+-------
r In ventory Control -r 3.5. 2 FREQUENCY In accordance with the Survei 11 ance Frequency  
              -&R- 3 . 5. 2. 6   Verify each valve credited for                                                       In accordance       _____
~-
automatically isolating a penetration flow                                           with the path actuates to the isolation position on                                           Surveil lan ce an actual or simulated isolation signa l .                                           Frequency Control Program ISR 3.5.2.6 I 3 . 5. 2. 7    - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - -
Control Program SR 3.5.2.~----------------------+-------
ISR 3.5.2.6 I
-&R-
: 3. 5. 2.6 Verify each valve credited for In accordance
: 3. 5. 2. 7 automatically isolating a penetration flow with the path actuates to the isolation position on Surveil lan ce an actual or simulated isolation signa l.
Frequency  
- - - - - - - - - - - - - - - - - - -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 Survei 11 ance Frequency Control Program
Verify the required ECCS injection/spray subsystem can be manually operated.
            ========================================================== +-'
Control Program In accordance with the Survei 11 ance Frequency Control Program  
Quad Cities 1 and 2                                          3.5.2-6                              Amendmen t No. 273 / 268


PC I Vs 3.6.1.3 3.6       CONTAINMENT SYSTEMS 3.6.1.3           Primary Containment Isolation Valves CPCIVs)
==========================================================+-'
LCO     3.6.1.3                 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
Quad Cities 1 and 2 3.5.2-6 Amendment No. 273/ 268
APPLICABILITY:                   MODES 1, 2, and 3, W~eR     associate~ iRstr~meRtatioR is re~~ire~ to ~e OPERAgLE f)er LCD 2 . 2 . 8 . 1 , " Primary CoRtaiRmeRt IsolatioR I RstrnmeRtati OR ."
 
ACTIONS
3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves CPCIVs)
PC I Vs 3.6.1.3 LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, W~eR associate~ iRstr~meRtatioR is re~~ire~ to ~e OPERAgLE f)er LCD 2. 2. 8. 1, "Primary CoRtaiRmeRt IsolatioR I RstrnmeRtati OR."
ACTIONS  
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1.
: 2. Separate Condition entry is allowed for each penetration flow path.
Penetration flow paths may be unisolated intermittently under administrative controls.
: 3.     Enter app l icable Conditions and Required Actions for systems made inoperable by PCIVs.
: 2.
: 4.     Enter app l icable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.
Separate Condition entry is allowed for each penetration flow path.
CONDITION                                             REQUIRED ACTION                              COMPLETION TIME A.     ---------NOTE--------                           A.1             Isolate the affected                      4 hours except Only app l icable to                                           penetration flow path                    for main steam penetration flow paths                                          by use of at least                       l in e with two or more                                                one closed and PC I Vs.                                                        de-activated automatic valve, closed manual valve,                     8 hours for main One or more                                                    blind flange, or                         steam line penetration flow paths                                          check valve with flow with one PCI V                                                  through the valve inoperab l e for reasons                                        secured.
: 3.
other than Condition D.                                    AND (continued)
Enter appl icable Conditions and Required Actions for systems made inoperable by PCIVs.
Quad Cities 1 and 2                                                  3.6.1.3-1                             Amendment No. 199/195
: 4.
Enter appl icable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.
CONDITION A.  
---------NOTE--------
A.1 Only appl icable to penetration flow paths with two or more PC I Vs.
One or more penetration flow paths with one PCI V inoperabl e for reasons other than Condition D.
AND Quad Cities 1 and 2 REQUIRED ACTION Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
COMPLETION TIME 4 hours except for main steam l in e 8 hours for main steam line (continued) 3.6.1.3-1 Amendment No. 199/195  


PC I Vs 3 . 6 . 1.3 AC TI ONS CON DIT ION                 REQU IRED AC TI ON                      COM PLE TI ON TI ME
ACTI ONS CON DIT ION
: c.   (con t inued)           C. 2     - - - - - - - - NOT ES- - - - - - - -
: c.
: 1. I so l at i on dev i ces in high rad i ation areas may be verif i ed by use of adm i ni s t rat i ve means .
(con t inued)
: 2.     I so l at i on devices that are locked, sea l ed, or oth erw i se secured may be verified by use of administrat i ve mea ns .
C. 2 D.
Verify th e affec t ed                 Once per 31 days penetra t ion fl ow path i s i solated .
MS IV leakage rate D. 1 not with i n li mit.
D. MS I V leakage rate      D. 1      Restore leakage ra t e                 8 hours no t with i n li mit.              to withi n l i mit .
E.
E. Required Action and      E. 1      Be in MODE 3 .                         12 hours associated Comp l et ion Time of Cond iti on A,  AND B' C, or D no t met-+A-MQQi; +/-, 2 , er 3 .      E.2      Be i n MOD E 4 .                       36 hours Quad Ci t i es 1 and 2              3 . 6.1.3-4                             Amendment No . 273/ 268
Required Action and E. 1 associated Comp l et ion Time of Cond iti on A, AND B' C, or D not met-+A-MQQi; +/-, 2, er 3.
E.2 Quad Ci t i es 1 and 2 REQU IRED AC TI ON
- - - - - - - - NOT ES- - - - - - - -
: 1.
I so l at i on dev i ces in high rad i ation areas may be verif i ed by use of adm i ni st rat i ve means.
: 2.
I so l at i on devices that are locked, sea l ed, or oth erwi se secured may be verified by use of administrat i ve mea ns.
Verify th e affec t ed penetra t ion fl ow path i s i solated.
Restore leakage ra t e to withi n l i mit.
Be in MODE 3.
Be i n MOD E 4.
PC I Vs 3. 6. 1.3 COM PLETI ON TI ME Once per 31 days 8 hours 12 hours 36 hours 3. 6.1.3-4 Amendment No. 273/ 268  


AC Sources-Shutdown 3.8.2 SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.
SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                           FREQUENCY SR   3.8.2.1 t
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.2.1 AC Sources-Shutdown 3.8.2 FREQUENCY The following SRs are applicable for
                              -------------------------------------- ~
--------------------------------------~
The following SRs f.ef'- AC sources required to be OPERABLE t-J:T.e.             In accordance are applicable for SRs ef SfJcci fi ca ti eA 3 . 8 . 1 , CJ\CCfJt                 with applicable SR 3 . 8 . 1 . 9 , SR 3 . 8 . 1 . 13 , SR 3 . 8 . 1 . 19 ,     SRs                -t-SR 3 . 8 . 1 . 20 , aA8 SR 3 . 8 . 1 . 21 , ape afJfJl i casl e .
f.ef'- AC sources required to be OPERABLE t-J:T.e.
SR 3.8.1.1             SR 3.8.1.6 SR 3.8.1.2            SR 3.8.1.10 SR 3.8.1.3            SR 3.8.1.11 SR 3.8.1.4            SR 3.8.1.15 SR 3.8.1.5            SR 3.8.1.17 Quad Cities 1 and 2                              3.8.2-5                     Amendment No. 273/268
SRs ef SfJcci fi ca ti eA 3. 8. 1, CJ\\CCfJt In accordance with applicable t
SR 3.8. 1. 9, SR 3.8. 1. 13, SR 3.8. 1. 19,
SR 3.8. 1. 20, aA8 SR 3.8. 1. 21, ape SRs
-t-afJfJl i casl e.
SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 Quad Cities 1 and 2 SR 3.8.1.6 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.15 SR 3.8.1.17 3.8.2-5 Amendment No. 273/268  


ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.3-122a B 3.3-122b 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 3.3-122j B 3.3-168 B 3.3-169 B 3.3-225 B 3.3-228 B 3.3-229 B 3.5-17 B 3.5-18 B 3.5-19 B 3.5-22 B 3.5-23 B 3.5-24 B 3.8-35 B 3.8-36 B 3.8-39
ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.3-122a B 3.3-122b 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 3.3-122j B 3.3-168 B 3.3-169 B 3.3-225 B 3.3-228 B 3.3-229 B 3.5-17 B 3.5-18 B 3.5-19 B 3.5-22 B 3.5-23 B 3.5-24 B 3.8-35 B 3.8-36 B 3.8-39  


RPV Water Inventory Control Instrumentation B 3.3.5.2 B 3.3     INSTRUMENTATION B 3.3 . 5 . 2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation BASES BACKGROUND           The RPV contains penetrations below the top of the active fuel (TAF) that have the potential to drain the reactor coolant inventory to below the TAF. If the water level should drop below the TAF , the ability to remove decay heat is reduced , which could lead to elevated cladding temperatures and clad perforation . Safety Limit 2 . 1 . l . 3 requires the RPV water level to be above the top of t he active irradiated fuel at all times to prevent such elevated cladding temperatures .
RPV Water Inventory Control Instrumentation B 3. 3. 5. 2 B 3.3 INSTRUMENTATION B 3.3. 5. 2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation BASES BACKGROUND CLINTON The RPV contains penetrations below the top of the active fuel (TAF) that have the potential to drain the reactor coolant inventory to below the TAF. If the water level should drop below the TAF, the ability to remove decay heat is reduced, which could lead to elevated cladding temperatures and clad perforation.
Technical Specifications are required by 10 CFR 50 . 36 to include limiting safety system settings (LSSS) for variables that have significant safety functions . LSSS are defined by the regulation as " Where a LSSS is specified for a variable on which a safety limit has been placed , the setting must be chosen so that automatic protective actions will correct the abnormal situation before a Safety Limit (SL) is exceeded ."
Safety Limit 2. 1. l. 3 requires the RPV water level to be above the top of t he active irradiated fuel at all times to prevent such elevated cladding temperatures.
The Analytical Limit is the limit of the process variab l e at which a safety action is initiated to ensure that a SL is not exceeded. Any automatic protection action that occurs on reaching the Analytical Limit therefore ensures that the SL is not exceeded . However , in practice , the actual settings for automatic protection channels must be chosen to be more conservative than the Analytical Limit to account for instrument loop uncertainties related to the set t ing at which the automatic protective action would actually occur.
Technical Specifications are required by 10 CFR 50. 36 to include limiting safety system settings (LSSS) for variables that have significant safety functions.
The actual settings for the automatic isolation channels are the same as those established for the same functions in MODES 1 , 2 , and 3 in +/-rG.Q. ;;J ;;J 5 1 , " I!:merr;;rerH:;y GG..re. C.:wliHr;;T
LSSS are defined by the regulation as "Where a LSSS is specified for a variable on which a safety limit has been placed, the setting must be chosen so that automatic protective actions will correct the abnormal situation before a Safety Limit (SL) is exceeded."
                      &#xa3;ystem (I!:CC&#xa3; ) I HstnameHtatiGH 1 " G-.:i:: LCO 3 . 3 . 6 .1, " Primary Containment Isolation instrumentation. "
The Analytical Limit is the limit of the process variabl e at which a safety action is initiated to ensure that a SL is not exceeded.
With the unit in MODE 4 or 5 , RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses . RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2 . 1 . 1 . 3 and the fuel cladding barrier to prevent the release of radioactive material should a draining event occur.                         Under the definition of DRAIN TIME , some penetration flow paths may be excluded from the DRAIN TIME calculation if they will be 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 .
Any automatic protection action that occurs on reaching the Analytical Limit therefore ensures that the SL is not exceeded.
However, in practice, the actual settings for automatic protection channels must be chosen to be more conservative than the Analytical Limit to account for instrument loop uncertainties related to the sett ing at which the automatic protective action would actually occur.
The actual settings for the automatic isolation channels are the same as those established for the same functions in MODES 1, 2, and 3 in +/-rG.Q.  
;;J  
;;J 5 1,  
"I!:merr;;rerH:;y GG..re. C.:wliHr;;T  
&#xa3;ystem (I!:CC&#xa3; )
I HstnameHtatiGH 1 "
G-.:i:: LCO 3. 3. 6.1, "Primary Containment Isolation instrumentation. "
With the unit in MODE 4 or 5, RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses.
RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2. 1. 1. 3 and the fuel cladding barrier to prevent the release of radioactive material should a draining event occur.
Under the definition of DRAIN TIME, some penetration flow paths may be excluded from the DRAIN TIME calculation if they will be 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.
(continued)
(continued)
CLINTON                              B 3.3 - 122a                                 Rev i sion No .     ~
B 3.3-122a Revi sion No. ~  


RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES BACKGROUND          The purpose of the RPV Water Inventory Contro l (continued)      Instrumentation i s to suppo r t the requirements of LCO 3 . 5 . 2 ,
BASES BACKGROUND (continued)
                    " RPV Water Inventory Control , " and the definition of DRA I N TIME . There are functions that ~ r e qt1ir e 9 .f.G-T m:urnal iHitiatioH G--T- operatioH G..t: .t.f+e EGG.&#xa3;. iHj e .::tioH/e:pray gyJdgye:t s m r s qt1ir e 9 .t4 ~ OP.KRAJ;JJ;.,l!;'. b:f J..G.Q. ~ .a.HQ ~
APPLICABLE SAFETY ANALYSES, LCO,
fnH>::tioHe ~ support automatic iso l ation of Residua l Heat Removal subsys t em and Reac t or Water Clean u p system penetration flow path ( s ) on low RPV water level .
and APPLICAB I LI TY considered considered CLINTON RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2 The purpose of the RPV Water Inventory Control Instrumentation i s to suppor t the requirements of LCO 3. 5. 2,  
                    -+/-Re- RW Wa-t-9-r- IHu e Htory CoHtrol IHe:trt11+1 e HtatioH eYJd)dOrte:
" RPV Water Inventory Control, " and the definition of DRAI N TIME.
ops ratioH G..t: J,.o.w. pre e:e:yr g ~ ~ (J;.,PC&#xa3; ), J,.o.w. prs e:e:t1r e
There are functions that ~
                    .::oolaHt iHj e .::tioH (J;.,PCI ), .a.HQ ~ pr e e:e:t1r e ~ ~
r e qt1ire 9.f.G-T m:urnal iHitiatioH G--T-operatioH G..t:.t.f+e EGG.&#xa3;. iHj e.::tioH/e:pray gyJdgye:ts m r s qt1ire 9.t4 ~ OP.KRAJ;JJ;.,l!;'. b:f J..G.Q. ~  
(FIPC&#xa3; ) ~ gqnip1+19Ht iH u ol u gg .w.i.tf+/- ~ G..t: ~ gygtgmg                     .;i,..g.
.a.HQ ~
ggggrilds9 .i.H- .t.f+e ~ .f.G-T J..G.Q. ~ 5 ~
fnH>::tioHe ~
APPLICAB LE          With the unit in MODE 4 or 5 , RPV water inventory co n trol is SAFETY              not required to mitigate any events or accidents evaluated ANALYSES , LCO ,    in the safety analyses . RPV water invento r y con t rol is and APPLICAB I LI TY required in MO DE S 4 and 5 to protect Safe t y Limit 2 . 1 . l . 3 and the fuel c l adding barr i er to prevent t he release of radioactive material shou l d a draining event occur .
support automatic isol ation of Residua l Heat Removal subsys t em and React or Water Cleanup system penetration flow path (s ) on low RPV water level.  
A double - e n ded gui l lotine break of the Reactor Coolant considered System (RCS ) is not                         in MODES 4 and 5 due t o the r n reduced RCS pressure , reduced p ipin stresses , and ducti l e considered        piping systems . I nstead , an event is poe:tt1lat e 9 i n which a siHgle operator ~ G--T- initiating event a l lows draining of the RPV water inventory through a sing l e penetration flow path with the highest f l ow rate , or the s u m of the drain rates through mu l tiple penetration f l ow paths suscep t ible to a common mode fa i lure (e g , seismic e " eHt , +/-G-&& G..t: Horma l pm er , siHgle R-Yrn error ) . It is assumed , based on 1
-+/-Re-RW Wa-t-9-r-IHue Htory CoHtrol IHe:trt11+1e HtatioH eYJd)dOrte:
engineering judgment , that while in MODES 4 and 5 , one ECCS injection/spray subsystem can b e manua l ly init i ated to maintain adequate reactor vessel water l evel .
ops ratioH G..t: J,.o.w. pre e:e:yrg ~  
As discuss e d in Re f e rences 1 , 2 , 3 , 4 , and 5 , ope rating experience has shown RPV water inventory to be significant to public health and safety . Therefore , RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50 . 36 (c ) (2 ) (ii ) .
~
Permissive and interlock setpoints are genera l l y considered as nominal values without regard to measurement accuracy .
(J;.,PC&#xa3; ), J,.o.w. prs e:e:t1re
The specific App l icable Safety Ana l yses , LCO , and Applicability discussions are listed below on a Function by Function basis .
.::oolaHt iHj e.::tioH (J;.,PCI ),.a.HQ ~
(continued )
pre e:e:t1re ~  
CLINTON                                B 3.3 - 122b                                 Rev i s i on No . ~
~
(FIPC&#xa3; )  
~
gqnip1+19Ht iH uolugg.w.i.tf+/- ~
G..t: ~
gygtgmg.;i,..g.
ggggrilds9.i.H-.t.f+e ~  
.f.G-T J..G.Q.  
~ 5 ~
With the unit in MODE 4 or 5, RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses. RPV water inventor y cont rol is required in MODES 4 and 5 to protect Safet y Limit 2. 1. l. 3 and the fuel c l adding barri er to prevent t he release of radioactive material shoul d a draining event occur.
A double - e nded gui l lotine break of the Reactor Coolant System (RCS ) is not in MODES 4 and 5 due t o the rn reduced RCS pressure, reduced p ipin stresses, and ducti l e piping systems. I nstead, an event is poe:tt1late 9 i n which a siHgle operator ~
G--T-initiating event a l lows draining of the RPV water inventory through a singl e penetration flow path with the highest f l ow rate, or the s um of the drain rates through mu l tiple penetration f l ow paths suscept ible to a common mode fa i lure (e g, seismic e " eHt, +/-G-&& G..t: Horma l pm 1er, siHgle R-Yrn error ). It is assumed, based on engineering judgment, that while in MODES 4 and 5, one ECCS injection/spray subsystem can be manua l ly initi ated to maintain adequate reactor vessel water l evel.
As discuss e d in Re f e rences 1, 2, 3, 4, and 5, ope rating experience has shown RPV water inventory to be significant to public health and safety. Therefore, RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50. 36 (c ) (2 ) (ii ).
Permissive and interlock setpoints are general l y considered as nominal values without regard to measurement accuracy.
The specific App l icable Safety Ana l yses, LCO, and Applicability discussions are listed below on a Function by Function basis.
(continued)
B 3.3-122b Revi s i on No. ~  


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~ Ji P r t t ru id l i i ~ r t;f h f  
~~
t  


RPV Water Inventory Contro l                 I nstrumentat i on       ,f--
BASES APPLICABLE SAFETY ANALYSES, LCO,
B 3.3.5.2 BASES APPLICABLE          ~ ~                 Discharge HG-W =         bGW Allo11able Ealtws a-re- R-i-gl+/-
and APPLICAB I LI TY (continued)
SAFETY                e nough -t-o- e nsur e -t-Ba-t- -t-Be-       p-ump -t-1--Gw -ra-t-B -i-& suffici e nt .t-o-ANALYSES , LCO ,    prot e ct -t-Be- p-ump-,- ye-t, G-W       e nough -t-o- e nsur e -t-Ba-t- -t-Be- closure and APPLICAB I LI TY G-.t: -t-Be- minim um -t-1--Gw ~             -i-& in it i at e g -t-o- .a,.1.J,..o.w. .f.u.l..l. -t-1--Gw (continued)      .i.n.-t-o- -t-Be- ~
CLINTON RPV Water Inventory Contro l I nstrumentat i on  
                    ~               channel G-.t: .t.J:+/-. ~ Discharge ~ = bGW Fnnction -i-&
,f--
regnireGl -t-o- oo OPE1UB1E .if+ ll4GDE.&#xa3;. 4 .a-00 ~ ~ -t-Be- associateGI
B 3. 3. 5. 2  
                    ~ G-r ~ p-ump -i-& reguired -t-o- oo OPEP:AB1E b-y l,CQ. ~ .t-o-e nsur e -t-Be- -p-uHlp8- a--r-e- capabl e G-.t: inj e cting .i.n.-t-o- -t-Be- P: e actor Pr e ssur e Ee ss e l wH-e-H- manually initiat e g
~  
                    .J-,...a....,.. P:eactor   ~         Isolation Cooling (P:CIC)             &#xa3;torag e          ~
~
                    ~                 = bGW bGW -l-e-v-e .if+ -t-Be- RC-+/--C &#xa3;torag e +e-nk indicat e s -t-Be-una' railability G-.t: e.++ ag e quat e supply G-.t: mak e up ~ .f.r.Gfl'I
Discharge HG-W = bGW Allo11able Ealtws a-re-R-i-gl+/-
                    ~ normal sourc e                        Mormally -t-Be- sldction " al " e s b e tu ee n
e nough -t-o-e nsure -t-Ba-t- -t-Be-p-ump -t-1--Gw -ra-t-B -i-& sufficie nt.t-o-prote ct -t-Be-p-ump-,- ye-t, G-W e nough -t-o-e nsure -t-Ba-t- -t-Be-closure G-.t: -t-Be-minim um -t-1--Gw ~  
                    ~ ~ -t-Be- RC-+/--C &#xa3; torage +e-nk a--r-e- ~ ~ ~ .f.G-r ~
-i-& in it i at e g -t-o-
injection ~ w .t.a.k.@.n, .f.r.Gfl'I .t.J:+/-. RC-+/--C &#xa3;torage ~
.a,.1.J,..o.w..f.u.l..l. -t-1--Gw  
Flo1 '9 ''er , .i.ct .t.AA ~ ~ .if+ ~ RC-+/--C &#xa3;torage +e-nk ~
.i.n.-t-o- -t-Be- ~  
                    ~ a- pr e s e lect e d l e u e l , .f-i-r-8-t- -t-Be- suppr e ssion pG-G                       suction &#xa5;a-l-&#xa5;e- automatically op e ns , ~ -t-Be-n -t-Be- RC-+/--C &#xa3;torage
~
                    ~ sldction &#xa5;a-l-&#xa5;e- automatically clos e s                             -'+/--R--i-.s- e nsur e s -t-Ba-t-e.++ ag e guat e supply 4.f: mak e up ~ -i-& a " ailabl e -t-o- -t-Be- ~
channel G-.t:.t.J:+/-. ~
p.ldHlp-.-         M pr e " e nt losing suction -t-o- -t-Be- p-ump-,- -t-Be- suction
Discharge ~  
                    " al " es ~ interlockeg ~ -t-Ba-t- .t.AA gnppression pG-G suction
= bGW Fnnction -i-&
                    ~ ffi.U-.&#xa3;.t. ~ ~ before .t.AA RC-+/--C &#xa3;torag e +e-nk snction
regnireGl -t-o-oo OPE1UB1E.if+ ll4GDE.&#xa3;. 4.a-00 ~ ~  
                    ~ automatically clo8 e 8 RC-+/--C &#xa3;torage -'+/-'-a+l-k hB&#xa5;e-l- = bGW eignal8 a--r-B initi a ted -f-r-Gm. -t-wB
-t-Be-associateGI  
                    -l-e-v-e tranBmitter8                 ~ ~ -i-& arranged .,s.u.G-fi, .t.f+.a.t. either tranem.itter .a.AA a88ociated ~ .c-a-n ~ -t-Be- 8uppre88ion pG-G 8Uction ~ -t-o- ~ .a.00 -t-Be- RC-+/--C &#xa3;torage -'+/-'-a+l-k 8uction
~
                    ~ -t-o- cloee
G-r ~
                    -'+/-'-AA RC-+/--C &#xa3;torage +e-nk be-&#xa5;e-+/-- = bGW Function 7\llo' rabl e .\la-1-uB
p-ump -i-& reguired -t-o-oo OPEP:AB1E b-y l,CQ. ~  
                    -i-& B-i-g-A enough -t-o- ensure adeguate p-ump suction fIB.a-G wB-i-1-e wa-te-r -i-& be-i-ng -t-a-keH- .f.r.Gfl'I -t-Be- RC-+/--C &#xa3;tor age -'+/-'-aFl-k-,...
.t-o-e nsure -t-Be- -p-uHlp8-a--r-e-capable G-.t: inj e cting.i.n.-t-o- -t-Be-P: e actor Pre ssure Ee ss e l wH-e-H-manually initiate g  
                    ~               channel8 G-.t: -t-Be- RG+/-G &#xa3;torage -'+/-'-a+l-k hB&#xa5;e-l- = bGW Function a--r-B ~             requireGI -t-o- ~ OPEP:l\BlE wH-e-H- JWG&#xa3;. -i-& required -t-o- ~
.J-,...a....,..
0.PEP:l\BlE -t-o- fulfill ffie requirementB 4.f: l,CO ~ 3 2 , ~ -i-&
P:eactor ~
align e g -t-o- -t-Be- RC-+/--C &#xa3;torag e ~ ~ -t-Be- RC-+/--C &#xa3;torage +e-nk wa-te-r -l-e-v-e -i-& f+O.t. Hithin -t-Be- li mit8 G-.t: .&#xa3;R ~ 3 2 ~
Isolation Cooling (P:CIC) &#xa3;torage ~  
~  
= bGW bGW -l-e-v-e.if+ -t-Be-RC-+/--C &#xa3;torage +e-nk indicate s -t-Be-una'railability G-.t: e.++ ag e quate supply G-.t: make up ~  
.f.r.Gfl'I  
~
normal source Mormally -t-Be-sldction " al" e s b e tueen
~  
~  
-t-Be-RC-+/--C &#xa3; torage +e-nk a--r-e- ~  
~  
~  
.f.G-r ~
injection ~
w.t.a.k.@.n,.f.r.Gfl'I.t.J:+/-. RC-+/--C &#xa3;torage ~
Flo1 '9''er,.i.ct.t.AA ~  
~  
.if+ ~
RC-+/--C &#xa3;torage +e-nk ~  
~
a-pre s e lecte d l e u e l,.f-i-r-8-t- -t-Be-suppre ssion pG-G suction &#xa5;a-l-&#xa5;e-automatically ope ns, ~  
-t-Be-n -t-Be-RC-+/--C &#xa3;torage  
~
sldction &#xa5;a-l-&#xa5;e-automatically clos e s  
-'+/--R--i-.s-e nsure s -t-Ba-t-e.++ ag e guate supply 4.f: make up ~  
-i-& a" ailabl e -t-o- -t-Be- ~
p.ldHlp-.-
M pre " e nt losing suction -t-o- -t-Be-p-ump-,- -t-Be-suction  
" al" es ~
interlockeg ~ -t-Ba-t-.t.AA gnppression pG-G suction  
~
ffi.U-.&#xa3;.t. ~ ~
before.t.AA RC-+/--C &#xa3;torage +e-nk snction  
~
automatically clo8 e 8 RC-+/--C &#xa3;torage -'+/-'-a+l-k hB&#xa5;e-l- = bGW eignal8 a--r-B initi a ted -f-r-Gm. -t-wB  
-l-e-v-e tranBmitter8  
~  
~  
-i-& arranged.,s.u.G-fi,.t.f+.a.t. either tranem.itter.a.AA a88ociated ~  
.c-a-n ~  
-t-Be-8uppre88ion pG-G 8Uction ~  
-t-o- ~  
.a.00 -t-Be-RC-+/--C &#xa3;torage -'+/-'-a+l-k 8uction  
~  
-t-o-cloee  
-'+/-'-AA RC-+/--C &#xa3;torage +e-nk be-&#xa5;e-+/--
=
bGW Function 7\\llo' rabl e.\\la-1-uB  
-i-& B-i-g-A enough -t-o-ensure adeguate p-ump suction fIB.a-G wB-i-1-e wa-te-r -i-& be-i-ng -t-a-keH-.f.r.Gfl'I -t-Be-RC-+/--C &#xa3;tor age -'+/-'-aFl-k-,...  
~
channel8 G-.t: -t-Be-RG+/-G &#xa3;torage -'+/-'-a+l-k hB&#xa5;e-l- = bGW Function a--r-B ~
requireGI -t-o- ~ OPEP:l\\BlE wH-e-H-JWG&#xa3;. -i-& required -t-o- ~
0.PEP:l\\BlE -t-o-fulfill ffie requirementB 4.f: l,CO ~ 3 2, ~  
-i-&
aligne g -t-o- -t-Be-RC-+/--C &#xa3;torage ~  
~  
-t-Be-RC-+/--C &#xa3;torage +e-nk wa-te-r -l-e-v-e -i-& f+O.t. Hithin -t-Be-limit8 G-.t:.&#xa3;R  
~ 3 2  
~
(continued )
(continued )
CLINTON                                        B 3.3 - 122d                                   Rev i s i on No .             ~
B 3.3-122d Revi s i on No. ~  


RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES APPLICABLE          ~ .J-.-.G-..-               .fW.C&#xa3;- ~ Diacharge l?r e aatire                 #.i-gR- (Bypaaa ) a-00 SAFETY              .fW.C&#xa3;- &#xa3;ygt e m HB-W Ra--t-e = -hGW (Bypagg )
BASES APPLICABLE SAFETY ANALYSES, LCO,
ANALYSES , LCO ,
RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2  
and APPLICAB I LI TY ~ miI:1imt1m .f..l.g..w. i1:rntrt1m.e Hta &re- prg" ig e g w prgt e ct .t.AA (continued)     .fW.C&#xa3;- p.blmp .f.r.GHl g" e rh e atiHg :wfi.ef+ .t.AA p.blmp -i-& ope ratiHg a.H-G
~  
                    .t.AA agggciat e g iHj e ctioH ~ -i-& ~ ~ ~ ~
.J-.-.G-..-
mi Him ' m .f..l.g..w. ~ ~ -i-& op eH e g ~ J,..Q.w .f..l.g..w. a.H-G ~
.fW.C&#xa3;- ~
1 p.blmp gigch:uge pre gg11re ~ a e i::ia e g , a.H-G .t.AA ~ -i-&
Diacharge l?re aatire  
atitomatically cloaed ~ -t-00 .f..l.g..w. -r-a-ffi -i-& ade qtiate w prgt e ct .t.AA p.blmp G-r- -t-R-e- diacharg e pre aatir e -i-& J,..Q.w (iHdicatiHg .t.AA .fW.C&#xa3;- p.blmp -i-& ~ gp e ratiHg )
#.i-gR-(Bypaaa ) a-00  
GHe-       .f..l.g..w. traHam.itt e r -i-& ~ w g e t e ct .t.AA ~ &#xa3;ygt e m' g
.fW.C&#xa3;- &#xa3;ygtem HB-W Ra--t-e = -hGW (Bypagg )
                    .f..l.g..w.   .r.a.t.-.-     ~ ~ -i-& ;;i rraHge g ~ .t.J:J..e.t. .t.AA traHam.itter catia e a .t.AA miHim11m ~ ~ .t.Q. ~ prg u ig g g .t.AA .fW.CS p.blmp diacharg e preaatire , a e Haed fl-&#xa5; aHgtJ:J.er traHamitt e r , -i-&
and APPLICAB I LI TY ~
                    ~ e Hgtigh ( iHdicatiHg .t.AA p.blmp -i-& ope ratiHg )                                   ~ ~
miI:1imt1m.f..l.g..w. i1:rntrt1m.e Hta &re-prg" ige g w prgte ct.t.AA (continued)  
W-i-+/- ~ .t.AA miHimtim .f..l.g..w. ~ GR-Ge- .t.AA cloatire a e tpgiHt
.fW.C&#xa3;-
                    -i-& e 2c c e e g e g            ~ ~ W-i-+/- .a-1-&G ~ ~ .fW.C&#xa3;- pbl-Hlp gigchaP3e pr e aatir e g e cr e aaiHg ~ -t-R-e- ge tpoiHt )
p.blmp.f.r.GHl g" e rhe atiHg :wfi.ef+.t.AA p.blmp -i-& ope ratiHg a.H-G CLINTON
                    ~ ~                       &#xa3;ygt e m. HB-W ~ = -hGW a.H-G ~ ~ Diach;;irge l?regg11re               = #.i-gR- Allgo;;il?le ~ -i-& ~ eHongh w eHanre
.t.AA agggciate g iHj e ctioH ~  
                    .t.J:J..e.t. pbl-Hlp .f..l.g..w. -r-a-t.e -i-& atiffici e Ht w prot e ct -t-f+/-e. pt!-ffip-,- -'fe-l-J,..Q.w e ngtigh w e natir e .t.J:J..e.t. .t.AA cloaure G-f .t.AA m.inimum .f..l.g..w.
-i-& ~  
                    ~ -i-& iHitiate d w e-l-1-Gw -f.bl-l .f..l.g..w. -i-H-t-9 .t.AA GG-re-.--
~  
                    ~ ~ ~                             Diacharge l?r e ggnr e        #.i-gR- Zl ll011ct1?l e  ~     -i-&
~  
                    .g.g.t. ~                 9H0 1gh w 9Ha ti rg .t.J:J..e.t. .t.AA ~ W-i-+/- ~
~
1 w ~
mi H im 1 'm.f..l.g..w. ~  
                    ~             .t.fi..e. ~ -i-& ~ op e r;;itiHg GHe- channel G-f e-aBB- Functign -i-& required .t.G- Be- OJ?EgABLE wf+/-BB-
~  
                    .fW.CS -i-&             r e qtiir e d w Be- OJ?Eg?l &#xa3;J LE fl-&#xa5; bGG ~ -i-n ~ 4-
-i-& opeHe g ~
                    .a-00 .a.,..
J,..Q.w.f..l.g..w. a.H-G ~
(continued )
p.blmp gigch:uge pre gg11re ~
CLINTON                                              B 3.3 - 122e                                   Rev i s i on No . ~
ae i::ia e g, a.H-G.t.AA ~  
-i-&
atitomatically cloaed ~  
-t-00.f..l.g..w. -r-a-ffi -i-& adeqtiate w prgte ct.t.AA p.blmp G-r- -t-R-e-diacharge pre aatire -i-& J,..Q.w (iHdicatiHg.t.AA.fW.C&#xa3;- p.blmp -i-& ~
gpe ratiHg )
GHe-
.f..l.g..w. traHam.itte r -i-& ~
w ge t e ct.t.AA ~  
&#xa3;ygtem' g  
.f..l.g..w..r.a.t.-.-
~  
~  
-i-& ;;i rraHge g ~  
.t.J:J..e.t..t.AA traHam.itter catia e a.t.AA miHim11m ~  
~  
.t.Q. ~
prguiggg.t.AA.fW.CS p.blmp diacharge preaatire, ae Haed fl-&#xa5; aHgtJ:J.er traHamitte r, -i-&  
~
e Hgtigh (iHdicatiHg.t.AA p.blmp -i-& ope ratiHg )  
~  
~
W-i-+/- ~  
.t.AA miHimtim.f..l.g..w. ~
GR-Ge-.t.AA cloatire ae tpgiHt  
-i-& e 2c ce e ge g  
~  
~
W-i-+/-.a-1-&G ~  
~  
.fW.C&#xa3;- pbl-Hlp gigchaP3e pre aatire ge cre aaiHg ~  
-t-R-e-ge tpoiHt )  
~  
~  
&#xa3;ygte m. HB-W ~  
= -hGW a.H-G ~  
~
Diach;;irge l?regg11re = #.i-gR-Allgo;;il?le ~  
-i-& ~
eHongh w eHanre  
.t.J:J..e.t. pbl-Hlp.f..l.g..w. -r-a-t.e -i-& atifficie Ht w prote ct -t-f+/-e. pt!-ffip-,- -'fe-l-J,..Q.w e ngtigh w e natire.t.J:J..e.t..t.AA cloaure G-f.t.AA m.inimum.f..l.g..w.  
~  
-i-& iHitiate d w e-l-1-Gw -f.bl-l.f..l.g..w. -i-H-t-9.t.AA GG-re-.--
~  
~  
~
Diacharge l?re ggnre
#.i-gR-Zl ll011ct1?le ~  
-i-&  
.g.g.t. ~
9H0 11gh w 9Ha ti rg.t.J:J..e.t..t.AA ~
W-i-+/- ~
w ~  
~  
.t.fi..e. ~  
-i-& ~
ope r;;itiHg GHe-channel G-f e-aBB-Functign -i-& required.t.G-Be-OJ?EgABLE wf+/-BB-
.fW.CS -i-& r e qtiire d w Be-OJ?Eg?l &#xa3;JLE fl-&#xa5; bGG ~  
-i-n ~
4-
.a-00.a.,..
(continued)
B 3.3-122e Revi s i on No. ~
 
BASES RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2 APPLICABLE RHR System Iso l ation SAFETY ANALYSES, LCO,
4--.-e- -
Reactor Vessel Water Level -
Low. Level 3 and APPLICAB I LI TY (continued)
The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water l evel isol ation instrumentation prior to the RPV water level being equal to the TAF.
The Reactor Vessel Water Level -
Low, Level 3 Function is onl y required to be OPERABLE when automat ic isolation of the associated RHR penetration f l ow path is credited in cal culating DRAIN TIME.
CLINTON Reactor Vessel Water Leve l -
Low, Level 3 signals are initiated from four level transmitters (two per trip system) that sense the d i fference between the pressure due to a constant column of water (reference l eg ) and the pressure due to the actua l water level (variable leg ) in the vessel.
While four channels (two channels per trip system) of the Reactor Vessel Water Leve l -
Low, Level 3 Function are available, only two channels (al l 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, Leve l 3 Al l owable Value (LCO 3. 3. 1. 1 ),
since the capabi l ity to cool the fue l may be threatened.
(continued)
B 3.3-122f Revi s i on No
. ~  


RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES APPLICABLE           RHR System Iso l ation SAFETY ANALYSES , LCO ,     4--.-e- - Reactor Vessel Water Level - Low . Level 3 and APPLICAB I LI TY (continued)     The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water l evel iso l ation instrumentation prior to the RPV water level being equa l to the TAF . The Reactor Vessel Water Level - Low , Level 3 Function is on l y required to be OPERABLE when automa t ic isolation of the associated RHR penetration f l ow path is credited in ca l culating DRAIN TIME .
BASES RPV Water Inventory Control I nstrumentation B 3. 3. 5. 2 APPLICABLE Reactor Water Cleanup (RWCU) System I solation SAFETY ANALYSES, LCO,  
Reactor Vessel Water Leve l - Low , Level 3 signals are initiated from four level transmitters (two per trip system) that sense the d i fference between the pressure due to a constant column of water (reference l eg ) and the pressure due to the actua l water level (variable leg ) in the vesse l.
~
While four channels (two channels per trip system ) of the Reactor Vessel Water Leve l - Low , Level 3 Function are available , only two channels (al l in the same trip system )
- Reactor Vessel Water level -
are required to be OPERAB LE .
Low Low, Level 2 and APPLICAB I LI TY (continued)
The Reactor Vessel Water Level - Low , Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low , Leve l 3 Al l owable Value (LCO 3 . 3 . 1 . 1 ),
The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level be i ng equal t o the TAF.
since the capabi l ity to cool the fue l may be threatened .
The Reactor Vessel Water Level -
(continued )
Low Low, Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration f l ow paths associated with the RWCU System.
CLINTON                              B 3.3 - 122f                  Rev i s i on No . ~
ACT I ONS CLINTON Reactor Vessel Water Leve l -
Low Low, Leve l 2 i s 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 actua l water level (variable l eg ) in the vessel.
While four channels (t wo channels per trip system) of the Reactor Vessel Water Level -
Low, Level 2 Function are avai l able, onl y two channels (al l in the same trip system) are required to be OPERABLE.
The Reactor Vessel Water Level -
Low Low, Leve l 2 Allowab l e Value was chosen to be the same as the ECCS Reactor Vessel Water Level -
Low Low, Level 2 Al lowab l e Va l ue (LCO 3. 3. 5. 1 ), since the capabil i ty to cool the fue l may be threatened.
The Reactor Vessel Water Level -
Low Low, Leve l 2 Function is onl y required t o be OPERABLE when automatic i solat ion of the associated penetration flow path is credited in calcul ating DRAIN TIME.
A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels.
Section 1. 3, Completion Times, speci fies t hat once a Condition has been entered, subsequent divisions,
s ubsystems, compone nts, or variables e xpre sse d i n the Condition discovered to be inoperabl e or not wi thin limits will not result i n separate entry into the Condi tion.
Section 1. 3 also specifies that Requ i red Actions cont inue to apply for each additional failure, with Completi on Times based on initial entry into the Condi tion.
However, t he Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory measures for separate inoperable Condi tion entry for each inoperable RPV Water Inventory Control instrumentation channel.
(continued)
B 3.3-122g Revi s i on No. ~  


RPV Water Inventory Contro l I nstrumentation B 3.3.5.2 BASES APPLICABLE          Reactor Water Clean u p (RWC U) System I solation SAFETY ANALYSES , LCO ,     ~ - Reactor Vessel Water level - Low Low , Level 2 and APPLICAB I LI TY (continued)      The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water leve l be i ng equal t o 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 f l ow paths associated with the RWCU System .
BASES ACTIONS (continued)
Reactor Vessel Water Leve l - Low Low , Leve l 2 i s initiated from two channels per trip system that sense the difference between the press u re due to a constan t column of water (reference leg ) and the pressure due to the actua l water level (variable l eg ) in the vessel . While four c h annels (t wo channels per trip system ) of the Reactor Vessel Water Level - Low , Level 2 Function are avai l able , on l y two channels (al l in the same trip system) are required to be OPERABLE .
IA.1. A.2.1. and A.2.2 A.2.1 CLINTON RPV Water Inventory Control I nstrumentation B 3. 3. 5. 2 P:si;;p;iirs 8 AstiGH A-.-l-8irs -;=;tg ~
The Reactor Vessel Water Level - Low Low , Leve l 2 Allowab l e Value was chosen to be the same as the ECCS Reactor Vessel Water Level - Low Low , Level 2 Al lowab l e Va l ue (LCO 3 . 3 . 5 . 1 ) , since the capabil i ty to cool the fue l may be threatened .
.i.fi.t.G..:tJ:+e. apprgpriats CeH8itieH r s f s r s H-;;e g ffi ~
The Reactor Vessel Water Level - Low Low , Leve l 2 Function is on l y required t o be OPERABLE wh en automatic i sola t ion of the associated penetration flow path is credited in calcu l ating DRAIN TIME .
~
ACT I ONS            A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels .
~ 5 2 - 1
Section 1 . 3 , Completion Times , spec i fies t h at once a Condition has been entered , subsequent divisions ,
~
s u bsys tems , compone nts , or variables e xpr e ss e d i n the Condition discovered to be inoperab l e or not wi thin limits will not result i n separate entry into the Condi tion .
appli-;;abls Cm:i.8iti91:1 r e f e r e H-;;0 8 ffi.:tJ:+e. ~
Section 1 . 3 also specifies that Requ i red Actions con t inue to apply for eac h additional failure , with Complet i on Times based on initia l entry into the Condi tion . However , t h e Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory meas u res for separate inoperable Condi tion entry for each inoperable RPV Water Inventory Contro l instrumentation channel .
.i.& FttH-;=;tiGH 8epe H8 e Ht
~
~
~,;J:ieiHHQl.i..e. 8ieQ9" HQ8 iHGp@reiblg, CGH8itiGH A.i.&
eHts:rng.f.G+.t.J:i.a.t; QA&lJ'.l.J'.l.91 ~
i;n*gu iggg.f.G+ tr;;i!'.l.gfgr w.t.00 apprgpriate &#xa3;ttbseqtt@Ht CGHditiGH
~~
" 2 1, """ ~
RHR System Iso l ation, Reactor Vesse l Water Leve l -
Low Leve l 3, and Reactor Water Cleanup System, Reactor Vessel Water Level -
Low Low, Level 2 functions are applicable when automat ic isolati on of the associated penetrati on f~
low path is credited in calcu lating Drain Time.
If t he A.1 instrumentation i s inoperable, Requi red Action ~ irects immediate action to place t he channe l in trip.
With the inoperable c hannel in the t ripped condition, t he remaining channel will iso l ate the penetration f l ow path on low water If both channels are inoperable and p l aced in tr i p,
flow path wi ll be isolated.
Al ternat ive l y,
1--~'-"+J..U..J;;,f;i"&deg;"-_....(;..i;.-..c;~~..,.........,o--,E'e-6f'\\:H:-lE'e-~ t he associated pen et ration.-----.
f l ow path (s )
be i mmediat ely declared incapable of IA.2.2 I a u tomat ic isolat i on.
Re quired Action ~
directs initiat ing action to ca l culate DRAIN TIME.
The calcul ation cannot credit automatic isolation of the affected
-+-
penetration flow path (s ).
t" bG-W-reagtgr " 98891 pr988ttrs 8igHal8 a..r.e- ~
.a...s-psrmi88ius8
.f.G+.:tfi.e. +/-G.w pr988t1T9 EG.C.&#xa3;. iHj98ti9H/8pray 8t1B8]'8t9m H\\3.Httal ir:iitiatiGH fttH-;=;tiGH8 U
.t.f:i...i.& psrmi8eiue.i.& iHGperabls,
maJ'.l.ttal iJ'.l.itiatiGJ'.l. &f. m
.i.& prgfl.ibiteg Tl:lergfgrg,.:tJ:+e.
pe rmi88i" O Hltl--&t be-pla-;;gd ffi.:tJ:+e. -t-r-i-p QGHditiGH Pitl:iiH 00-tl-T-r W-i-t-R-.:tJ:+e. permi88i" e ffi.:tJ:+e. -t-r-i-p ggr:iditign, manttal iHitia tiGH may-be-perfgrmed
-P-r-i-G-r-
-t-G-plaGiHg.:tJ:+e.
permi88iue ffi.:tJ:+e. tripped 89HditiGH 1  
.:tJ:+e. epsratgr G-a-R.t.a.k-e maHttal 8GHtrgl &f..:tJ:+e. ~
~
.:tJ:+e. iHj98ti9H ~
-t-G-iHj98t
~
.i.fi.t.G..:tJ:+e. R-.J2-',l..,...
~
Cgmple tiGH.T.Htte-G-f. ~
.i.& iHts H8 e 8 -t-G-.a-1--1-G.w.:tJ:+e.
gperatgr ~
-t-G-O" alttate.a.fi..lf 8i8QG" ere8 iHGperabilitie8 ~
-t-G- ~
.:tJ:+e.
-;=; J:i a H He l ffi.t.r.i.p...-
(continued )
(continued )
CLINTON                                  B 3.3 - 122g                    Rev i s i on No . ~
B 3.3-122h Revi s i on No. ~  


RPV Water Inventory Contro l                            I nstrumentation B 3.3.5.2 BASES ACTIONS (continued)
BASES ACTIONS (continued)
P: si;;p;iirs 8 AstiGH A-.-l- 8ir s -;=;tg ~ .i.fi.t.G. .:tJ:+e. apprgpriat s CeH8itieH r s f s r s H-;; e g ffi ~ ~ ~ 5 2 - 1                                                ~ appli-;;abl s Cm:i.8iti91:1 r e f e r e H-;; 0 8 ffi .:tJ:+e. ~ .i.& FttH-;=;tiGH 8 e p e H8 e Ht
CLINTON RPV Water Inventory Control I nstrumentation  
                            ~ ~ ~ ,;J:ieiHHQl .i..e. 8ieQ9" HQ8 iHGp@reiblg , CGH8itiGH A .i.&
.+---
eHts:rng .f.G+ .t.J:i.a.t; QA&lJ'.l.J'.l.91 ~ i;n*gu iggg .f.G+ tr;;i!'.l.gfgr w .t.00 apprgpriat e &#xa3;ttbseqtt@Ht CGHditiGH
B 3. 3. 5. 2 gequired Actiona -Id-.--+/- aH-G ~
                          ~~                                           ~
~
IA.1 . A.2.1. and A.2.2
intended w enaure Wa-t-appropriate actiona a.re- ~  
                                          " 2 1 , """                                                                                                        -+-
.i.f. multiple, inoperal2le cH.annela PitH.in -t.H-e-
RHR System Iso l ation , Reactor Vesse l Water Leve l - Low Leve l 3 , and Reactor Water Cleanup System , Reactor Vessel Water Level - Low Low , Level 2 functions are applicable when automa t ic isolat i on of the associated penetrat i on f~                                                   low path is credited in calc u lating Drain Time .                                                     If t h e                    A.1 instrumentation i s inoperable , Requ i red Action ~ irects immediate action to place t he channe l in trip . With the inoperable c h annel in the t ripped condition , t h e remaining channel will iso l ate the penetration f l ow path on low water A.2.1                              If both channels are inoperable and p l aced in tr i p ,
&aHte-Function reault.i..n.a.J,..g..g..g. G-f-a tt tom at i c 8 u c ti on.,g.w..ap ~
flow path wi ll be isolated . Al terna t ive l y ,
-t.H-e- ~
1--~'-"+J..U..J;;,f;i"&deg;"-_....(;..i;.-..c;~~..,.........,o--,E'e-6f'\:H:-lE'e-~ t h e associated pen et ration .-----.
8'/ 8 t em.f.r-OHl -t.H-e-RG.J.G ator;;igg.t.a.+/-+k w  
f l ow path (s )                        be i mmedia t ely declared incapable of                                      IA.2.2 I a u toma t ic isolat i on . Re q uired Action ~ d irects initia t ing action to ca l culate DRAIN TIME .                                                    The calcu l ation cannot credit automatic isolation of the affected penetration flow path ( s ) .                                                                                                    t" bG-W- reagtgr " 98891 pr988ttrs 8igHal8 a..r.e- ~ .a...s- psrmi88ius8
.t.J+g anpprgggion ~
                            .f.G+ .:tfi.e. +/-G.w pr988t1T9 EG.C.&#xa3;. iHj98ti9H/8pray 8t1B8]'8t9m H\3.Httal ir:iitiatiGH fttH-;=;tiGH8                                U .t.f:i...i.& psrmi8eiue .i.& iHGperabls ,
~  
maJ'.l.ttal iJ'.l.itiatiGJ'.l. &f.                    m            .i.& prgfl.ibiteg            Tl:lergfgrg , .:tJ:+e.
~
p e rmi88i " O Hltl--&t be- pla-;; g d ffi .:tJ:+e. -t-r-i-p QGHditiGH Pitl:iiH                              00-tl-T-r W-i-t-R- .:tJ:+e. permi88i " e ffi .:tJ:+e. -t-r-i-p ggr:iditign , manttal iHiti a tiGH may- be- perfgrmed                                            -P-r-i-G-r- -t-G- plaGiHg .:tJ:+e.
gygtgm ~
permi88iue ffi .:tJ:+e. tripped 89HditiGH 1 .:tJ:+e. epsr a tgr G-a-R .t.a.k-e maHttal 8GHtrgl &f. .:tJ:+e. ~ ~ .:tJ:+e. iHj98ti9H ~ -t-G- iHj98t
oo GleclareGl iAopenele uiUi.iA.1. 00.u+/- G+ -t.H-e- ~
                            ~ .i.fi.t.G. .:tJ:+e. R-.J2-',l..,...
p.ump attction ~
                            ~          Cgmpl e tiGH .T.Htte- G-f. ~ .i.& iHt s H8 e 8 -t-G- .a-1--1-G.w .:tJ:+e.
oo aligned w -t-00 attppreaaion -pGG-1-., aince,.i.f.
gper a tgr ~ -t-G- O" alttate .a.fi..lf 8i8QG" ere8 iHGperabilitie8                                                    ~
aligned, -t.H-e-function -i-.s-already performed
                            -t-G- ~ .:tJ:+e. -;=; J:i a HHe l ffi .t.r.i.p...-
-'+/-'-Re-.1. OOtJ.r. CompletioA Um -i-.s-acceptal2le 12ecatt8e.i..:t; minimizeg -t.H-e-
(continu ed )
.r.i..g..J.;, G-f- ~  
CLINTON                                              B 3.3 - 122h                                                    Rev i s i on No .   ~
~
nee9e9 Pitfiout.a..i:+ a9eqttate
~
aonrcg w.fi.i.l.g. allouiAg.t.i.m ~
r@atoratioA G+
;;iligAmeAt G-f- ~
p.ump attctioA w -t.H-e-attppreaaioA ~
U
.a..i:+ ~
G+ ~
Qigcf:i.arge ~
= W.w. 12ypa88 function G-.r.  
~
&#xa3;ygtem Qigcf:i.arge Preaaure = filgl+/- G+ ~
~
=
W.w.
12 yp a 8 8 f n Act i o A -i-.s-i Ao pg r a 12 lg, -t-00.r.- -i-.s-.a.;r.i..a.k -t-fi.a-t- ~
a88ociate9 ~
p.ump ~
o" QrHeat ~
.:t.AA p.ump -i-.s-operating aH-G -t.H-e-aaaociated injection.v-a-l&#xa5;e- -i-.s-fi.G.-t- -f-tt-l-1-y-Gpe-fi.--
-+/--H-tJi...i-& condition, -t.H-e-operator -Ga-H- -t-a-k-e manttal control G-f- -t.H-e-p.ump aH-G -t.H-e-injection.v-a-l&#xa5;e-w enattre -t.H-e-p.ump ~
fi.G.-t-o" erH.eat
~
.:f-4 OOtJ.r. Compl@tion ~
.w..a.a. cfioggn w ~  
.t.i.m ~  
-t-00 op>Hator w e " alnate aH-G repair.a.f+&#xa5; 9iaCO" >He9 inoperal2ilitiea p-r-i-o-r w declaring -t.H-e-affected 8t1BByBtem inoperable.  
-'+/-'-Re-Completion Um+/--& appropriate g-i-&#xa5;BB- -t.H-e-ability w manually &t-a-r-t- -t.H-e- ~
pttmp..s- -a-00 GpB-R -t.H-e-inj ection ualueg.a.& neceBBary w enBure -t.H-e-affer;:;ted p.uHlf' OOe..s-fi.G.-t-ouer!::i.eat W-i-t-R -t.H-e-geqttired Ar;:;tion a-BG aBBOGiated Completion Um G-f-ConditionB G, If., G+ E fi.G.-t-me-t,- -t.H-e-aBBOGiated ~
injer;:;tion/Bpray BttbByBtem ma.:r be inGapable G-f-performing -t.H-e-intended fttnGtion, a-BG ~
be der;:;lared inoperable immediately (continued )
B 3.3-122i Revi sion No. ~  


RPV Water Inventory Contro l I nstrumentation                          .+---
BASES (continued)
B 3.3.5.2 BASES ACTIONS (continued) gequired Actiona -Id-.--+/- aH-G ~ ~ intended w enaure Wa-t-appropriate actiona a.re- ~ .i.f. multiple , inoperal2le cH.annela PitH.in -t.H-e- &aHte- Function reault .i..n .a .J,..g..g..g. G-f-a tt tom at i c 8 u c ti on .,g.w..ap ~ -t.H-e- ~ 8'/ 8 t em .f.r-OHl -t.H-e- RG.J.G ator;;igg .t.a.+/-+k w .t.J+g anpprgggion ~ ~ ~ gygtgm ~
SURVEILLANCE REQUIREMENTS CLINTON RPV Water Inventory Control Instrumentation B 3. 3. 5. 2 The following SRs apply to As ~  
oo GleclareGl iAopenele uiUi.iA .1. 00.u+/- G+ -t.H-e- ~ p.ump attction ~ oo aligned w -t-00 attppreaaion -pGG-1-., aince , .i.f.
.H+ -t-00 beginning &t: -t-00 $R.&-r -t-00 SR-&.f.G-+/-' each RPV Water Inventory Control instrument Function -a&#xa3;-B ~
aligned , -t.H-e- function -i-.s- already performed
in -t-fi.B SR-& column &t: Table 3. 3. 5.2 - 1.
                -'+/-'-Re- .1. OOtJ.r. CompletioA Um -i-.s- acceptal2le 12ecatt8e .i..:t; minimizeg -t.H-e- .r.i..g..J.;, G-f- ~ ~ nee9e9 Pitfiout .a..i:+ a9eqttate
SR 3.3.5.2.l Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred.
                ~ aonrcg w.fi.i.l.g. allouiAg .t.i.m ~ r@atoratioA G+
A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.
                ;;iligAmeAt G-f- ~ p.ump attctioA w -t.H-e- attppreaaioA ~
It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.
U      .a..i:+ ~        G+ ~ Qigcf:i.arge ~ = W.w. 12ypa88 function G-.r.
Signific ant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.
                ~              &#xa3;ygtem Qigcf:i.arge Preaaure = filgl+/- G+ ~ ~ = W.w.
A CHANNEL CHECK guarantees that undetected outright channel failure is limited; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL FUNCTIONAL TEST.
12 yp a 8 8 f n Act i o A -i-.s- i Ao pg r a 12 lg , -t-00.r.- -i-.s- .a .;r.i..a.k -t-fi.a-t- ~
Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertaint ies,
a88ociate9 ~ p.ump ~ o" QrHeat ~ .:t.AA p.ump -i-.s-operating aH-G -t.H-e- aaaociated injection .v-a-l&#xa5;e- -i-.s- fi.G.-t- -f-tt-l-1-y-Gpe-fi.--        -+/--H- tJi...i-& condition , -t.H-e- operator -Ga-H- -t-a-k-e manttal control G-f- -t.H-e- p.ump aH-G -t.H-e- injection .v-a-l&#xa5;e- w enattre -t.H-e-p.ump ~ fi.G.-t- o" erH.eat
including indication and readability.
                ~          .:f-4 OOtJ.r. Compl@tion ~ .w..a.a. cfioggn w ~ .t.i.m ~ -t-00 op>Hator w e " alnate aH-G repair .a.f+&#xa5; 9iaCO" >He9 inoperal2ilitiea p-r-i-o-r w declaring -t.H-e- affected 8t1BByBtem inoperable. -'+/-'-Re- Completion Um+/--& appropriate g-i-&#xa5;BB- -t.H-e-ability w manually &t-a-r-t- -t.H-e- ~ pttmp..s- -a-00 GpB-R -t.H-e-inj ection ualueg .a.& neceBBary w enBure -t.H-e- affer;:;ted p.uHlf' OOe..s- fi.G.-t- ou er!::i.eat W-i-t-R -t.H-e- geqttired Ar;:;tion a-BG aBBOGiated Completion Um G-f-ConditionB G, If., G+ E fi.G.-t- me-t,- -t.H-e- aBBOGiated ~
If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.
injer;:;tion/Bpray BttbByBtem ma.:r be inGapable G-f- performing -t.H-e-intended fttnGtion , a-BG ~ be der;:;lared inoperable immediately (co n tinued )
CLINTON                                         B 3.3 - 122i                                Rev i sion No .        ~
 
RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES  (continued)      The following SRs apply to SURVEILLANCE        As ~       .H+ -t-00 beginning &t: -t-00 $R.&-r -t-00 SR-& .f.G-+/-' each RPV REQUIREMENTS        Water Inventory Control instrument Function -a&#xa3;-B ~ in -t-fi.B SR-& column &t: Table 3 . 3. 5 .2 - 1 .
SR   3.3.5.2.l Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred . A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels . It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value .
Signifi c ant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious . A CHANNEL CHECK guarantees that undetected outright channel failure is limited; thus , it is key to verifying the instrumentation continues to operate properly between each CHANNEL FUNCTIONAL TEST .
Agreement criteria are determined by the plant staff , based on a combination of the channel instrument uncertain t ies ,
including indication and readability .           If a channel is outside the criteria , it may be an indication that the instrument has drifted outside its limit .
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
The CHANNEL CHECK supplements less formal , but more frequent , checks of channels during normal operational use of the displays associated with the channels required by the LCO .
The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.
(continued)
(continued)
CLINTON                              B 3.3 - 122j                         Revision No .     ~
B 3.3-122j Revision No. ~  


Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1 BASES ACTIONS        K .1 and K. 2 (continued)
BASES ACTIONS (continued)
If the channel is not restored to OPERABLE status or placed in trip , or any Required Action of Condition I or J is not met and the associated Completion Time has expired , the plant must be placed in a MODE or other specified condition in which the LCO does not apply .                     This is done by placing the p l ant in at l east MODE 3 within 12 hours and in MODE 4 within 36 hours . The allowed Completion Times are reasonable , based on operating experience , to reach t he required plant conditions from full power conditions in an order l y manner and without challenging plant systems .
CLINTON Primary Containment and Drywell Isolation Instrumentation B 3. 3. 6. 1 K.1 and K. 2 If the channel is not restored to OPERABLE status or placed in trip, or any Required Action of Condition I or J is not met and the associated Completion Time has expired, the plant must be placed in a MODE or other specified condition in which the LCO does not apply.
L . 1 and L . 2 If the channel is not restored to OPERABLE status wi t hin the allowed Completion Time , the associated SLC subsystem(s) is declared inoperable or the RWCU System is isolated .                                     Since this Function is required to ensure that t he SLC System performs its intended function , sufficient remedial measures are provided by declaring the associated SLC subsystem inoperable or isolating the RWCU System .
This is done by placing the p l ant in at l east MODE 3 within 12 hours and in MODE 4 within 36 hours.
The Completion Time of 1 hour is acceptable because it minimizes risk while allowing sufficient time for personnel to isolate the RWCU System . RWCU isolation is achieved by closing 1G33F001 or 1G33F004 , which are the containment isolation valves associated with this isolation function .
The allowed Completion Times are reasonable, based on operating experience, to reach t he required plant conditions from full power conditions in an order l y manner and without challenging plant systems.
M. l r M-.-2-,- M J 1 , M J 2 , M J J ,           a-AG~
L. 1 and L. 2 If the channel is not restored to OPERABLE status wi t hin the allowed Completion Time, the associated SLC subsystem(s) is declared inoperable or the RWCU System is isolated.
If the channel is not restored to OPERABLE status or placed in trip within the allowed Completion Time , the associated penetration flow path should be isolated (i . e ., closing either 1El2 - F008 or 1El2 - F009) . However , if the shutdown cooling function is needed to provide core cooling , these Required Actions allow the penetration flow path to remain uniso l ated provided action is immediately initiated t o restore the channel to OPERABLE status G-F w firo u ide ffie.a+l                 ~ Gontrol G-f. flOtential radioaGti u e releases .                           ~
Since this Function is required to ensure that t he SLC System performs its intended function, sufficient remedial measures are provided by declaring the associated SLC subsystem inoperable or isolating the RWCU System.
inGhades enstuin~ seGondary Gontainment .i...s- Ol?Kl~~Al3I.:e;:: ; .a.t.
The Completion Time of 1 hour is acceptable because it minimizes risk while allowing sufficient time for personnel to isolate the RWCU System.
e-a-&t- G-H-e- &#xa3; t::rn sH> y Ga-& Tr e a tm en t +&#xa3;.G.T+. s yg s y s t em .i...s- 0 pg g 71 13 I.E ;
RWCU isolation is achieved by closing 1G33F001 or 1G33F004, which are the containment isolation valves associated with this isolation function.
                .a.AG seGoAGla:ry GoAtaii:imeflt isolatioi:i Gafla9ility (i e , .a.t.
M. l r M-.-2-,- M J 1, M J 2, M J J, a-AG~
e-a-&t- G-H-e- isolation &#xa5;a-l&#xa5;e- a-AG assoGiated inst:rt1mentation -a--:r-e OJ?Eg7\J3I,E G-F ~ aGGeflta9le 21slmii:iist:r21ti u e GoAt:rols w 21ssn:re isol21tioi:i Gafla9ility ) .i-1:+ ~ seGoAGla:ry Goi:it21ii:imei:it a-AG seGondary Gontainmeflt 9yflass fJenetration ~ ~ ~
If the channel is not restored to OPERABLE status or placed in trip within the allowed Completion Time, the associated penetration flow path should be isolated (i. e., closing either 1El2-F008 or 1El2 - F009).
isolated tJ+a.t. .i...s- asst1med .t.G .9e isolated .t.G miti~ate (co n tinued )
However, if the shutdown cooling function is needed to provide core cooling, these Required Actions allow the penetration flow path to remain uniso l ated provided action is immediately initiated t o restore the channel to OPERABLE status G-F w firouide ffie.a+l ~
CLINTON                                  B 3 . 3 - 168                               Rev i sion No . +/--G.=4
Gontrol G-f. flOtential radioaGtiue releases.  
~
inGhades enstuin~ seGondary Gontainment.i...s-Ol?Kl~~Al3I.:e;:: ;.a.t. e-a-&t-G-H-e-
&#xa3; t::rn sH> y Ga-& Tr e a tm en t +&#xa3;.G.T+. s yg s y s t em.i...s- 0 pg g 71 13 I.E ;  
.a.AG seGoAGla:ry GoAtaii:imeflt isolatioi:i Gafla9ility (i e,.a.t. e-a-&t-G-H-e-isolation &#xa5;a-l&#xa5;e-a-AG assoGiated inst:rt1mentation -a--:r-e OJ?Eg7\\J3I,E G-F ~
aGGeflta9le 21slmii:iist:r21tiu e GoAt:rols w 21ssn:re isol21tioi:i Gafla9ility ).i-1:+ ~
seGoAGla:ry Goi:it21ii:imei:it a-AG seGondary Gontainmeflt 9yflass fJenetration ~  
~  
~
isolated tJ+a.t..i...s-asst1med.t.G.9e isolated.t.G miti~ate (continued )
B 3. 3-168 Revi sion No. +/--G.=4  
 
BASES ACTIONS the channel is restored to OPERABLE status.
CLINTON Pri mary Contai nment and Drywe l l Iso l ation I nstrumentat i on B 3. 3. 6. 1 M. l, M-.--6, M J 1, M J 2, M J J,.a-AG M-.--J-.-4 (conti nued )
radioactiuity r e l e a&#xa3; e &#xa3; Tu-i ~
Pe-pe rforme d aS-a+/-+
admiI:1i2trati" e cJ::J.e ck, b&#xa5; e xaminiI:1g ~
~ ~
information, w de t e rmiA e.i..f. ~
compone nt&#xa3;.a.r.e.g.y..j; Q..f ge p rice ~
mainte nance ~ ~
r e a&#xa3;On&#xa3;
.J.t..;i,..a. fl4t.
ngcggg:;iry w pgrform.t.J::J..- &#xa3;HP'9ill:;incgg nggdgd w dgmon2tr:;itg
.t.00 0PE1U'1H1.ITY Q..f.t.00 Gompon0i:i.tg
.r..f.,.. J::J.o\\'G" Gr, d-Wf r e quire d Gompoi:i.e i:i.t.;i,..a. iAope rabl e, -tRe-A -i-t-m-&t-Pe-r e 2tore d w
QpEg 71 ~.bE 2tatu&#xa3;
.I-fl-.t.fl..i-& Ga-&e-r ~
&#xa3;uP'e illance &#xa3; ~
Aee4 w Pe-pe rforme d w r e 2tore ~
Gompone nt w QPEg 11 ~1.E gtatug Ii:i. additioi:i.,.a..t. J,..e..a.,s..t. ' ~
.i.f+ ~
~
Goi:i.taii:i.me nt p e raoi:i.ne l.a.i+/-. ~
m-&t-Pe-Gloa e d
~
c l oa e d
.a.i+/-. ~
Q.Q..g.r. Gomplgtgg.t.J::J..- boHi:i.dary ~
coi:i.trol Q..f potGi:i.ti:;il radioaGti" G rglg:;iggg W.i.tJl..t.00 appropri:;itg admii:i.iatrati" e Gontrol&#xa3; J::\\oPe " er, -tR-e Gloa e d Q.Q..g.r. &a-1:+ ~
ope ne d inte rmitte ntly ~
~
.a-AG ~
Tu-i allouance.;i,..a.
acG eptable 4u-e-w ~
Aee4 ~
Gontainment aGCe &#xa3;&#xa3;.a-AG 4u-e-w
~
~
progre &#xa3;&#xa3;ioi:i. Q..f e ue nt&#xa3; ~
~
r e ault ~
.a.
r e aGtor " e &#xa3;&#xa3; e l draii:i.douA e" e i:i.t g e actor " e &#xa3;&#xa3; e l draindoPn e" e nt&#xa3; ~
fl4t. Pe-expe Gte d w r e n;i l t.i.f+ ~
imme diate rglg:;igg G-f appr9Giablg fi&#xa3;&#xa3;ion prodnGt&#xa3; w
.t.J::J..- Goi:i.t:;iinmgi:i.t
:;itmoapJ::J.grg Act i ons must continue unti l;f\\.a..l.l. rgq11irgmgi:i.t&#xa3; Q..f
.tR--i Condition.a.r.e &#xa3;ati2fie d I
N. l, N. 2. 1, and N. 2. 2 If the channel is not restored to OPERABLE status or placed in trip within the allowed Comp letion Time, the associated penetration flow path (s ) shoul d be isol ated (Required Action N. l ).
I solating the affected penetration flow path (s ) accompl ishes the safety function of the inoperable instrumentation.
Alternately, the p l ant must be placed in a condition in which the LCO does not apply.
If applicable,
movement of recent l y irradiated fuel assemblies (i. e., fuel that has occupied part of a critical reactor core wi t hin t he previous 24 hours ) must be i mmediate l y suspended.
Suspension of these activit i es shal l not preclude completi on of movement of a component to a safe condition.
(continued)
B 3. 3-1 69 Revi s i on No. G.=2-


Pr i mary Conta i nment and Drywe l l Iso l ation I nstrumentat i on B 3.3.6.1 BASES ACTIONS    M. l ,    M-.--6, M J 1 , M J 2 , M J J , .a-AG M-.--J-.-4 (cont i nued )
BASES APPLICABLE SAFETY ANALYSES,
radioacti u ity r e l e a&#xa3; e &#xa3;              Tu-i ~ Pe- p e rforme d aS- a+/-+
LCO, and APPLICABILITY CLINTON LOP Instrumentation B 3. 3. 8. 1 l. a, l. b, 2. a, 2.b.
admiI:1i2trati" e cJ::J. e ck , b&#xa5; e xaminiI:1g ~ ~ ~
4.1 6 kV Emergency Bus Undervoltage (Loss of Voltage) (continued)
information , w d e t e rmiA e .i..f. ~ compone nt&#xa3; .a.r.e .g.y..j; Q..f ge p ric e ~ maint e nanc e ~ ~ r e a&#xa3;On&#xa3;                                          .J.t. .;i,..a. fl4t.
The Division 3 4. 16 kV Emergency Bus Loss of Voltage Function 120 - volt Basis trip setpoint is
ngcggg:;iry w pgrform .t.J::J..- &#xa3;HP ' 9ill:;incgg nggdgd w dgmon2tr:;itg
~ 67 volts and
                .t.00 0PE1U'1H1.ITY Q..f .t.00 Gompon0i:i.tg                      .r..f.,.. J::J.o\'G" Gr , d-Wf r e quir e d Gompoi:i. e i:i.t .;i,..a. iAop e rabl e , -tRe-A -i-t- m-&t- Pe- r e 2tore d w QpEg 71 ~.bE 2tatu&#xa3; .I-fl- .t.fl..i-& Ga-&e-r ~ &#xa3;uP ' e illanc e &#xa3; ~
~ 78 volts.
Aee4 w Pe- p e rform e d w r e 2tore ~ Gompon e nt w QPEg 11 ~1.E gtatug          Ii:i. additioi:i. , .a..t. J,..e..a.,s..t. ' ~ .i.f+ ~ ~
Six channels of 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) Function per associated emergency bus for Divisions 1 and 2 and four channels for Division 3 are only required to be OPERABLE when the associated DG is required to be OPERABLE to ensure that no single instrument failure can preclude the DG function.
Goi:i.taii:i.m e nt p e raoi:i.n e l .a.i+/-. ~ m-&t- Pe- Gloa e d                                  ~ c l oa e d
(Six channels input to each of the Division 1 and Division 2 DGs and four channels input to the Division 3 DG.
                .a.i+/-. ~ Q.Q..g.r. Gomplgtgg .t.J::J..- boHi:i.dary ~ coi:i.trol Q..f potGi:i.ti:;il radioaGti" G rglg:;iggg                        W.i.tJl. .t.00 appropri:;itg admii:i.iatrati" e Gontrol&#xa3; J::\oPe " er , -tR-e Gloa e d Q.Q..g.r. &a-1:+ ~
Each of the six channels for Division 1 and six channels for Division 2 is an inverse time delay relay.
ope n e d int e rmitt e ntly ~ ~ .a-AG ~ Tu-i allouanc e .;i,..a.
Each of these time delays are considered to be separate channels.
acG e ptabl e 4u-e- w ~ Aee4 ~ Gontainm e nt aGC e &#xa3;&#xa3; .a-AG 4u-e- w
For Divi sion 3, the Loss of Voltage Function logic inputs to a single time delay relay.
                ~ ~ progr e &#xa3;&#xa3;ioi:i. Q..f e u e nt&#xa3; ~ ~ r e ault ~ .a.
Thus,
r e aGtor " e &#xa3;&#xa3; e l draii:i.douA e " e i:i.t                g e actor " e &#xa3;&#xa3; e l draindoPn e " e nt&#xa3; ~ fl4t. Pe- e xp e Gt e d w r e n;i l t .i.f+ ~ imm e diat e rglg:;igg G-f appr9Giablg fi&#xa3;&#xa3;ion prodnGt&#xa3; w .t.J::J..- Goi:i.t:;iinmgi:i.t
only one time de l ay channel is associated with Division 3. )
:;itmoapJ::J.grg        Act i ons must continue unti l;f\.a..l.l. rgq11irgmgi:i.t&#xa3; Q..f
Refer to LCO 3. 8. 1, "AC Sources-Operating, " ~
                .tR--i Condition .a.r.e &#xa3;ati2fi e d                                      I the channel is restored to     N. l , N. 2 . 1 , and N. 2 . 2 OPERABLE status.
J.GG J g  
If the channel is not restored to OPERABLE status or placed in trip within the allowed Comp letion Time , the associated penetration flow path ( s ) shou l d be iso l ated (Required Action N. l ) .           I solating the affected penetration flow path (s ) accomp l ishes the safety function of the inoperable instrumentation . Alternately , the p l ant must be placed in a condition in which the LCO does not apply .                                           If a p plicable ,
~
movement of recent l y irradiated fuel assemblies (i . e ., fuel that has occupied part of a critical reactor core wi t hin t he previous 24 hours ) must be i mmediate l y suspended .
.!.!.AG &#xa3;9H:rggg &#xa3;l:J.Ht.bl9HA 1 " for Applicability Bases for the DGs.
Suspension of these activit i es shal l not preclude complet i on of movement of a component to a safe condition .
l. c, l. d, l. e, 2.c, 2. d, 2. e.
(continued )
4. 16 kV Emergency Bus Undervoltage (Degraded Voltage )
CLINTON                              B 3 . 3 - 1 69                                            Rev i s i on No . G.=2-
A reduced voltage condition on a 4.16 kV emergency bus indicates that while offsite power may not be completely lost to the respective emergency bus, power may be insuffic ient for starting large motors without risking damage to the motors that could disab l e the ECCS function.
Therefore, power supply to the bus is transferred from offsite power to onsite DG power when the voltage on the bus drops below the Degraded Voltage Function Allowable Values (degraded voltage with a time delay ).
This ensures that adequate power will be available to the required equipment.
The Bus Unde rvoltage Al l owable Value s are low e nough to prevent inadvertent power supply transfer, but high enough to ensure that sufficient power is available to the required equipment.
As stated above, the purpose of this instrumentation i s to ensure that sufficient power will be available to support the ECCS function during a LOCA.
During a LOCA, the ECCS and other safety systems will be initiated at the start of the event.
This l arge loading of the safety buses results in a voltage transient of (continued )
B 3. 3-225 Revision No. 4=J.  


LOP Instrumentation B 3.3.8.1 BASES APPLICABLE        l . a , l. b , 2 . a , 2.b . 4 .1 6 kV Emergency Bus Undervoltage SAFETY ANALYSES ,   (Loss of Voltage) (continued)
BASES ACTIONS (continued)
LCO , and APPLICABILITY      The Division 3 4 . 16 kV Emergency Bus Loss of Voltage Function 120 - volt Basis trip setpoint is ~ 67 volts and                    ~  78 volts .
SURVEILLANCE REQUIREMENTS CLINTON B.1 LOP Instrumentati on B 3. 3. 8. 1 If any Required Action and associated Completion Time is not met, the associated Function may not be capabl e of performing the intended function.
Six channels of 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) Function per associated emergency bus for Divisions 1 and 2 and four channels for Division 3 are only required to be OPERABLE when the associated DG is required to be OPERABLE to ensure that no single instrument failure can preclude the DG function .                 (Six channels input to each of the Division 1 and Division 2 DGs and four channels input to the Division 3 DG . Each of the six channels for Division 1 and six channels for Division 2 is an inverse time delay relay.      Each of these time delays are considered to be separate channels . For Div i sion 3 , the Loss of Voltage Function logic inputs to a single time delay relay . Thus ,
Therefore, the associated DG (s ) are declared inoperable immediately.
only one time de l ay channel is associated with Division 3 . )
This requires entry into applicable Conditions and Required Actions of LCO 3. 8. l ~
Refer to LCO 3 . 8 . 1 , "AC Sources-Operating, " ~ J.GG J g ~ '
l.CO] S l, which provide appropriate actions for the inoperabl e DG (s ).
                  .!.!.AG &#xa3;9H:rggg &#xa3;l:J.Ht.bl9HA 1 " for Applicabi li ty Bases for the DGs .
As noted at the beginning of the SRs, the SRs for each LOP Instrumentation Function are l ocated in the SRs column of Table 3. 3. 8.1-1.
l . c , l. d , l . e , 2.c , 2 . d , 2 . e . 4 . 16 kV Emergency Bus Undervoltage (Degraded Voltage )
The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, ent ry into associated Conditions and Required Actions may be delayed for up to 2 hours provided the associated Function maintains DG initiation capability.
A reduced voltage condition on a 4.16 kV emergency bus indicates that while offsite power may no t be completely lost to the respective emergency bus , power may be insuffi c ient for starting large motors without riski n g damage to the motors that could disab l e the ECCS function.
Upon completi on of the Surveillance,
Therefore , power supply to the bus is transferred from offsite power to onsite DG power when the voltage on the bus drops below the Degraded Voltage Function Allowable Values (degraded voltage with a time delay ). This ensures that adequate power will be available to the required equipment .
or expiration of the 2 hour allowance, the channel must be returned to OPERABLE status or the app l icabl e Condition entered and Required Actions taken.
Th e Bus Unde rvoltag e Al l owabl e Va lu e s ar e low e nough to prevent inadvertent power supply transfer , but high enough to ensure that sufficient power is available to the required equipment . As stated above , the purpose of this instrumentation i s to ensure that sufficient power will be available to support the ECCS function du rin g a LOCA .
SR 3. 3. 8. 1. 1 This SR has been deleted.
During a LOCA , the ECCS and other safety systems will be initiated at the start of the event . This l arge loading of the safety buses results in a voltage transient of (co n tinued )
SR 3. 3. 8. 1. 2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. For series Functions, i. e., for the degraded voltage relays in series with their associat ed delay timers, a separate CHANNEL FUNCTIONAL TEST is not required for each Function, provided each Function is tested.
CLINTON                                  B 3 . 3 - 225                          Revision No. 4=J.
A successfu l test of the required contact (s) of a channel relay may be performed by the verification of the change of state of a singl e contact of the relay.
Th is c l arifies what is an acceptable CHANNEL FUNCT I ONAL TEST of a relay.
This is acceptable because al l of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.
Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.
The Surveillance Frequency is control l ed under the Surveillance Frequency Control Program.
(continued)
B 3. 3-228 Revi sion No. -+/-4=6


LOP Instrumentat i on B 3.3.8.1 BASES ACTIONS        B .1 (continued)
BASES SURVEILLANCE REQUIREMENTS (continued)
If any Required Action and associated Completion Time is not met , the associated Function may not be capab l e of performing the intended function . Therefore , the associated DG (s ) are declared inoperable immediately . This requires entry into app li cable Conditions and Required Actions of LCO 3 . 8 . l ~ l.CO] S l , which provide appropriate actions for the inoperab l e DG ( s ).
REFERENCES CLINTON SR
SURVEILLANCE    As noted at the beginning of the SRs , the SRs for each LOP REQUIREMENTS    Instrumentation Function are l ocated in the SRs column of Table 3 . 3 . 8 .1-1.
: 3. 3. 8. 1. 3 LOP Instrumentati on B 3. 3. 8. 1 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.
The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances , en t ry into associated Conditions and Required Actions may be delayed for up to 2 hours provided the associated Function maintains DG initiation capab ili ty . Upon complet i on of the Surveillance ,
This test verifies the channel responds to the measured parameter within the necessary range and accuracy.
or expiration of the 2 hour allowance , the channel must be returned to OPERABLE status or the app l icab l e Condition entered and Required Actions taken .
CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.
SR    3 . 3 . 8 . 1. 1 This SR has been deleted .
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR   3 . 3 . 8 . 1. 2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function . For series Functions , i . e ., for the degraded voltage relays in series with their associa t ed delay timers , a separate CHANNEL FUNCTIONAL TEST is n ot required for each Fu nction , provided each Function is tested . A successfu l test of the required contact (s) of a channel relay may be performed by the verification of the change of state of a sing l e contact of the relay . Th is c l arifies what is an acceptable CHANNEL FUNCT I ONAL TEST of a relay . This is acceptable because al l of the other required contacts of the relay are verified by other Technical Specifications and non - Technical Specifications tests at least once per refueling interval with applicable extensions .
SR 3. 3. 8. 1. 4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel.
Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology .
The system functional testing performed in LCO 3. 8.1 e+l-4 J,,G.Q ~
The Surveillance Frequency is control l ed under the Surveillance Frequ ency Control Program .
overlaps this Surveil l ance to provide compl ete testing of the assumed safety functions.
(co n tinued)
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
CLINTON                                B 3 . 3 - 228          Rev i sion No . -+/-4=6
: 1.
USAR, Section 8. 3. 1.1. 2.
2.
USAR, Section 5. 2. 2.
3.
USAR, Section 6. 3. 3.
4.
USAR, Chapter 15.
5.
I P Calculati on 19-AN-1 9.
B 3. 3-229 Revi sion No. -+/-4=6  


LOP Instrumentat i on B 3.3.8.1 BASES SURVEILLANCE  SR  3. 3 . 8 . 1. 3 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor . This test verifies the channel responds to the measured parameter within the necessary range and accuracy . CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.
RPV Water Inventory Contro l B 3. 5. 2 B 3. 5 EMERGENCY CORE COOLING SYSTEMS (ECCS ), REACTOR PRESSURE VESSEL (RPV )
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC )
SR  3 . 3 . 8 . 1. 4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel . The system functional testing performed in LCO 3 . 8.1 e+l-4 J,,G.Q ~ overlaps this Surveil l ance to provide comp l ete testing of the assumed safety functions .
SYS TEM B 3. 5. 2 RPV Water I nventory Control BASES BACKGROUND APPLICABLE SAFETY ANALYSES The RPV con tains penetrations be l ow t h e top o f the active fuel (TAF ) t hat have the potential to drain the react or coo l ant inventory to be l ow the TAF.
The Surveillance Frequency is contro ll ed under the Surveillance Frequency Control Program .
If the water leve l should drop be l ow the TAF, the ability to remove decay heat is reduced, wh ich could lead to elevated cladding temperatures and c l ad perforation.
REFERENCES    1. USAR , Section 8 . 3 . 1.1. 2 .
Safety Limit 2. 1. l. 3 requires the RPV water l evel to be above the top of t he active irradiated f uel at all times to prevent such elevat ed cladding temperatures.
: 2. USAR , Section 5 . 2 . 2 .
With t h e unit in MODE 4 or 5, RPV water inventory contro l is not required to mitigate any events or accidents eva l uated in the safety analyses.
: 3. USAR , Section 6 . 3 . 3 .
RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2. 1. 1. 3 and the fuel c l adding barrier to prevent the re l ease of radioactive material to the environment should an unexpected draining event occur.  
: 4. USAR , Chapter 15 .
!considered I D gg n b l e ended qui:l,lotine break of the Reactor Coolant System (RCS ) is no~ p98ttt l atgg in MODES 4 and 5 due t o the reduced RCS pressure, reduced piping stresses, and ducti l e
: 5. I P Calculat i on 19 - AN - 1 9 .
....-~~~~~~~~-
CLINTON                            B 3 . 3 - 229            Rev i sion No . -+/-4=6
piping systems.
Instead, an event is considered in which an event that creates singlg gpgratgr m G-r-in i tiating event a l lows draining of a drain path through multiple vessel penetrations located below top of active fuel, such as or LCO CLINTON the RPV water inventory through a singl e penetration flow path with the highest f l ow rate, or the sum of the drain rates throu h mu l ti le enetration f l ow a h suscept ible a common mode fa i lure
(~
sgismi8 gugnt, loss of normal power, single human error ).
It is assumed, based on engin ring judgment, that while in MODES 4 and 5, on e l ow pre ssu e ECCS injection/spray subsyste m can maintain adequa e reactor vessel water level.
to As discussed in References 1, 2, 3, 4, and 5, operating experience has shown RPV water inventory to be significant to public health and safety.
Therefore, RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50. 36 (c ) (2 ) (ii ).
The RPV water l eve l must be controlled in MODES 4 and 5 to ensure that if an unexpected draining event should occur,
the reactor coolant water level rema i ns above the top of t he active irradiated f uel as required by Safety Limit 2. 1. 1. 3.
The Limiting Condition for Operation (LCO ) requires t he DRAIN TIME of RPV water inventory to the TAF to be ~ 36 hours.
A DRAIN TIME of 36 hours is considered reasonable to (con tinued )
B 3. 5-17 Revis i on No. ~


RPV Water Inventory Contro l B 3.5.2 B 3.5    EMERGENCY CORE COOLING SYSTEMS (ECCS ), REACTOR PRESSURE VESSEL (RPV )
BASES LCO (continued}
WATER INVENTORY CONTROL , AND REACTOR CORE ISOLATION COOLING (RCIC )
RPV Water Inventory Contro l B 3. 5. 2 identify and initiate action to mitigate unexpected draining of reactor coo l ant.
SYS TEM B 3.5.2  RPV Water I nventory Control BASES BACKGROUND        The RPV co n tains penetrations be l ow t h e top o f the active fuel (TAF ) t h at have the potential to drain the reac t or coo l an t inventory to be l ow the TAF .        If the water leve l should drop be l ow the TAF , the ability to remove decay heat is reduced , wh ich could lead to elevated cladding temperatures and c l ad perforation .          Safety Limit 2 . 1 . l . 3 requires the RPV water l evel to be above the top of t he active irradiated f u el at all times to prevent such eleva t ed cladding temperatures .
An event that cou l d cause l oss of RPV water inventory and result in the RPV water level reaching the TAF in greater than 36 hours does not represent a significant chal l enge to Safety Limi t 2. 1. 1. 3 and can be  
APPLICAB LE        With t h e unit in MODE 4 or 5 , RPV water inventory contro l is SAFETY ANALYS ES  not required to mitigate any events or accidents eva l uated in the safety analyses .          RPV water inventory control is required in MO DE S 4 and 5 to protect Safety Limit 2 . 1 . 1 . 3 and the fuel c l adding barrier to prevent the re l ease of radioactive material to the environment should an unexpected draining event occur .
.--~~~~~~ managed as part of normal plant operation.
      !considered        ID  gg n b l e ended qui:l,lotine break of the Reactor Coolant System (RCS ) is no~ p98ttt l atgg in MODES 4 and 5 due t o the reduced RCS pressure , reduced piping stresses , and ducti l e
from the control room aligned and OPERABILITY of the ECCS injection/spray subsystem includes any necessary valves, instrumentation, or controls needed to manually align and start the subsystem from the control room.
....-~~~~~~~~-            piping systems .      Instead , an event is considered in which an event that creates      singlg gpgratgr m            G-r- in i tiating event a l lows draining of the RPV water inventory through a sing l e penetration flow a drain path through path with the highest f l ow rate , or the sum of the drain multiple vessel            rates throu h mu l ti le enetration f l ow a h suscep t ible to penetrations located      a common mode fa i lure ( ~ sgismi8 g u gnt , loss of normal power , single human error ) .         It is assumed , based on below top of active        engin ring judgment , that while in MO DES 4 and 5 , o n e l ow fuel , such as            pr e ssu e ECCS injection/spray subsyst e m can maintain adequa e reactor vessel water level .
CLINTON One ECCS injection/spray subsystem is equire OPERABLE and capabl e of being manually started to provide defense - in - depth should an unexpected draining event occur.
or As discussed in References 1 , 2 , 3 , 4, and 5 , operating experience has shown RPV water inventory to be significant to public h ealth and safety .          Therefore , RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50 . 36 ( c ) (2 ) (ii ).
n ECCS injection/spray subsystem is defined as either one of the three Low Pressure Coo l ant Injection (LPCI }
LCO                The RPV water l eve l mu st be controlled in MODES 4 and 5 to ensure that if an unexpected draining event should occur ,
subsystems, one Low Pressure Core Spray (LPCS } System, or one High Pressure Core Spray (HPCS } System.
the reactor coolant water level rema i ns above the top of t he active irradiated f u el as required by Safety Limit 2 . 1 . 1 . 3 .
The LPCI s ubsys t em and the LPCS Sys t em cons i st of one motor driven pump, piping, and valves to transfer water from the suppression pool to the reactor pressure vessel (RPV ).
The Limiting Condition for Operation (LCO ) requires t he DRAIN TIME of RPV water inventory to the TAF to be ~ 36 hours.       A DRAIN TIME of 36 hours is considered reasonable to (co n tinued )
The HPCS System cons i sts of one motor dr i ven pump, piping, and valves to transfer water from the suppression poo l or RC I C storage tank to the RPV.
CLINTON                                  B 3 . 5 - 17                      Revis i on No .   ~
Management o f gas voids is important to ECCS injection/spray subsystem OPERABI LITY.
The LCO is modif i ed by a Note t hat al l ows a LPCI subsystem to be inoperabl e during a l ignment and operation for decay heat removal with reactor steam dome pressure less than t he residual heat removal cut - i n permissive pressure.
Th is is necessary since the RHR system is requ ired to operate in the shutdown coo l ing mode to remove decay heat and sensible heat from the reactor, and manual realignment from the shutdown cooling mode to t he LPC I mode cou l d r esul t i n pump cavitation and voiding in the suction piping, resulting in the potential to damage the RHR system, inc l uding wat er hammer.
One LPC I s ubsystem is a l lowed to be considered inoperable for this temporar y period, because in s h ut down cooling mode it i s fu l fil l i ng a decay heat remova l capaci t y f unction.
At these low pressures and decay heat levels, a reduced compl e ment of ECCS s ubsystems should provide the required core cooling, thereb y a l lowi ng operation of RHR shutdown coo l ing when necessary.
Becau se of the restrictions on DRAIN TI ME, sufficient time wil l be available fo l lowi ng an unexpected dra i ning event to manua l ly align and operate t he re quired LPCI subsystem to maintain RPV wat er inventory prior t o the RPV water l eve l reach ing the TAF.
(continued}
B 3. 5-18 Revis i on No. ~  


RPV Water Inventory Contro l B 3.5.2 BASES LCO                identify and initiate action to mitigate unexpected draining (continued}    of reactor coo l ant . An event that cou l d cause l oss of RPV water inventory and result in the RPV water level reaching the TAF in greater than 36 hours does not represent a significant chal l enge to Safety Limi t 2 . 1 . 1 . 3 and can be
BASES (continued)
                .--~~~~~~  managed as part of normal plant operation .
APPLICABILITY RPV Water Inventory Control B 3. 5. 2 "Instrumentation,"
aligned and                                                            from the control room One ECCS injection/spray subsystem is equire OPERABLE and capab l e of being manually started to provide defense - in - depth should an unexpected draining event occur .
RPV water inventory control is quired in MODES 4 and 5.
OPERABILITY of the           n ECCS injection/spray subsystem is defined as either one ECCS injection/spray       of the three Low Pressure Coo l ant Injection (L PCI }
Requirements on water inventory ntro l in other MODES are "ECCS, RPV Water r-~c f'7;o~n~t~a~i=.;n:;-e~d~;;i.;;n-;--;L;C;..0
subsystem includes          subsystems , one Low Pressure Core Spray (L PCS } System , or one High Pressure Core Spray (HPCS } System .           The LPCI any necessary valves,      s u bsys t em and the LPCS Sys t em cons i st of one moto r d ri ven instrumentation, or        pump , piping , and valves to transfer water from the controls needed to          suppression pool to the reactor press u re vessel (RPV ) .            The HPCS System cons i sts of one motor dr i ven pump , piping , and manually align and          valves to transfer water from the suppression poo l or RC I C start the subsystem        storage tank to the RPV . Management o f gas voids is from the control room.      important to ECCS injection/spray subsystem OPERABI LITY .
:....s;__~
The LCO is modif i ed by a Note t h at al l ows a LPCI subsystem to be inoperab l e during a l ignment and operation for decay heat removal with reactor steam dome pressure less than t h e residual heat removal cut - i n permissive pressure.           Th is is necessary since the RHR system is requ ired to operate in the shutdown coo l ing mode to remove decay heat and sensible hea t from the reactor , and manual realignment from the shutdown coo li ng mode to t h e LPC I mode cou l d r esu l t i n p ump cavitation and voiding in the suction piping , resulting in the potentia l to damage the RHR system , inc l uding wa t er hammer . One LPC I s u bsystem is a l lowed to be considered inoperable for this tempora r y p eriod , because in s h u t down cooling mode it i s fu l fil l i ng a decay heat remova l capaci t y f u nction . At these low pressures and decay h eat levels , a reduced comp l e ment of ECCS s u bsystems should provide the required core cooling , thereb y a l low i ng operation of RHR shutdown coo l ing when necessary . Becau se of the restrictions on DRAIN TI ME , sufficient time wil l be available fo l low i ng an unexpected dra i ning even t to manua l ly align and operate t h e re q uired LPCI subsystem to mai n tain RPV wa t er inventory prior t o the RPV water l eve l reach ing the TAF .
i
(co n tinued }
:>...n Section 3. 3, Inetr1,1mgntat.ign, and other LCOs in ::>ection._).,,, EC.CS.,.- ~
CLINTON                                  B 3 . 5 - 18                  Revis i on No .   ~
.a.n.Q ~
~
I nugntgry Inventory Control, Cgntrgl RPV water inventory control is required to protect and RCIC System."
Safety Limit 2. 1. 1. 3 which is applicab l e whenever irradiated fuel is in t h e reactor vessel.
ACTIONS CLINTON A. 1 and B. 1 If the required ECCS injecti on/spray subsystem i s inoperable, it must be res t ored to OPERABLE status within 4 hours.
In this Condition, t he LCO controls on DRAIN TI ME minimize the possibility that an unexpected dra i ning event could necessitate the use of the ECCS injection/spray subsystem, however the defense - in-depth provided by the ECCS injection/spray subsystem is lost.
The 4 hour Completion Time for restoring the requ i red ECCS i njection/spray subsys t em to OPERABLE status is based on engineering judgment that considers the LCO controls on DRAIN TIME and the low probabil i ty of a an unexpected draining event that would result in a l oss of RPV water i nventory.
If the inoperable ECCS injection/spray subsystem is not restored to OPERABLE status within the required Completion Time, action must be initiated immedi ately to establish a method of water i njection capab le of operating without offsite electrical power.
The method of water injection includes the necessary ins t r umentation and control s, water sources, and pumps and va l ves needed to add water to the RPV or refueling cavi ty should an unexpected draining event occur.
The method of water injection may be manually operated and may consist of one or more systems or s ubsys t ems, and must be able to access water inventory capabl e of maintaining the RPV water level above the TAF for
~ 36 hours.
If recircu l ation of injected water would occur,
i t may be credited in determining the necessary water volume.
(continued)
B 3. 5-19 Revis i on No. ~  


RPV Water Inventory Contro l B 3.5.2 "Instrumentation,"
BASES ACTIONS Required Actions D.2, D.3, and D.4 are considered to be met when secondary containment, secondary containment penetrations, and the Standby Gas Treatment System are OPERABLE in accordance with LCO 3.6.4.1, LCO 3.6.4.2, and LCO 3.6.4.3.
BASES  (continued )
CLINTON RPV Water Inventory Control B 3. 5. 2 0. 1, 0. 2, 0. 3, and 0. 4 (continued) operated and may consist of one or more additional method of water injection must be able to access water inventory capable of being injected to maintain the RPV water level above the TAF for ~ 36 hours.
APPLICABILITY        RPV water inventory control is                                        quired in MO DES 4 and 5 .
The additional method of water injection and the ECCS injection/spray subsystem may share all or part of the same water sources.
Requirements on water inventory                                        ntro l in other MODES are "ECCS, RPV Water r-~cf'7;o~n~t~a~i=.;n:;-e~d~;;i.;;n-;--;L;C;..0:....s;__~
If recirculation of injected water would occur, it may be credited in determining the required water volume.
i:>...n Section 3 . 3 , Inetr1,1mgntat.ign , and other LCOs in ::>ection ._) . ,,, EC.CS.,.- ~ .a.n.Q ~ ~ I n u gntgry Inventory Control,      Cgntrgl              RPV water inventory contro l is required to protect and RCIC System."        Safety Limit 2 . 1 . 1. 3 which is applicab l e whenever irradiated fuel is in t h e reactor vessel .
Should a draining event lower the reactor coolant level to below the TAF, there is potential for damage to the reactor fuel cladding and release of radioactive material.
ACTIONS              A . 1 and B . 1 If the required ECCS inject i on/spray subsystem i s inoperable , it must be res t ored to OPERABLE status within 4 h ours .            In this Condition , t h e LCO controls on DRAIN TI ME minimize the possibility that an unexpected dra i ning even t could necessitate the use of the ECCS injection/spray subsystem , however the defense - in - depth provided by the ECCS injection/spray subsystem is lost .                                     The 4 hour Completion Time for restoring the requ i red ECCS i njection/spray subsys t em to OPERABLE status is based on engineering judgment that considers the LCO controls on DRAIN TIME and the low probabil i ty of a an unexpected draining even t that would result in a l oss of RPV water i nventory .
Additional actions are taken to ensure that radi oactive material will be contained, diluted, and processed prior to being released to the environment.
If the inop erable ECCS injection/spray subsystem is not restored to OPERAB LE status within the required Completion Time , action must be initiated immed i ately to establis h a method of water i njection capab le of operating without offsite electrical power . The method of water injection includes the necessary ins t r umentation and contro l s , water sources , and pumps and va l ves needed to add water to the RPV or refueli n g cav i ty should an unexpected draining event occur .           The method of water injection may be manually operated and may consist of one or more systems or s u bsys t ems , and mu st be able to access water inventory capab l e of maintaining the RPV water level above the TAF for
The secondary containment provides a control volume into which fission products can be contained, diluted, and processed prior to release to the environment.
                        ~ 36 hours .                   If recircu l ation of injected water would occur ,
Required Action D. 2 requires that actions be immediately initiated to establish the secondary containment boundary.
i t may be credited in determining the necessary water volume .
With t he secondary containment boundary established, one SGT subsystem is capable of maintaining a negative pressure in the secondary containment with respect to the environment.
The secondary containment penetratio automatically Or secondary containment boundary.
Req requires that actions be immediately i nitiated to verify that each secondary containment pen ation flow path is isolated or to verify that it can be manually isolated from the control room.
Examples of manual isolation from the control room coul d include the use of manual isolation pushbuttons, control switches, or placing a sufficient number of radiation monitor channels in trip.
A secondary containment penetration flow path can be considered isolated when one barrier in the flow path is in place.
Examples of suitable barriers include, but are not limited to, a closed secondary containment isolation damper (SCIO), a closed manual valve, a blind flange, or another sealing device that sufficiently seals the penetration flow path.
The primary containment upper personnel airlock and other primary containment penetrations that bypass secondary containment are considered part of the secondary containment boundary ;
therefore, they must be considered when completing this action.
One SGT subsystem is capable of maintaining the secondary containment at a negative pressure with respect to the environment and filter gaseous releases.
Required Action 0. 4 requires that actions be immediately initiated to verify that at least one SGT subsystem is capable of being placed in operation.
The required verification is an administrative activity and does not require manipulation or testing of equipment.
(continued )
(continued )
CLINTON                                                            B 3 . 5 - 19                      Revis i on No . ~
B 3. 5-22 Revision No. G-=6


RPV Water Inventory Control B 3.5.2 BASES ACTIONS     0 . 1 , 0 . 2 , 0 . 3 , and 0 . 4    (continued) operated and may consist of one or more additional method of water injection must be able to access water inventory capable of being injected to maintain the RPV water level above the TAF for ~ 36 hours . The additional method of water injection and the ECCS injection/spray subsystem may share all or part of the same water sources . If recirculation of injected water would occur , it may be credited in determining the required water volume .
BASES ACTIONS (continued}
Should a draining event lower the reactor coolant level to below the TAF , there is potential for damage to the reactor fuel cladding and release of radioactive material.
SURVEILLANCE REQUIREMENTS closed and administratively controlled CLINTON E. 1 RPV Wate r Inventory Control B 3. 5. 2 If the Required Actions and associated Completion times of Conditions C or D are not met or if the DRAIN TIME is less than 1 hour, actions must be initiated immediately to restore the DRAIN TIME to 2 36 hours.
Additional actions are taken to ensure that rad i oactive material will be contained , diluted , and processed prior to being released to the environment .
In this condi t ion,
The secondary containment provides a control volume into which fission products can be contained , diluted , and processed prior to release to the environment. Required Action D. 2 requires that actions be immediately initiated to establish the secondary containment boundary . With t he secondary containment boundary established , one SGT subsystem is capable of maintaining a negative pressure in the secondary containment with respect to the environment.
there may be insufficient time to respond to an unexpected draining event to prevent the RPV water inventory from reaching the TAF.
The secondary containment penetratio                        automatically Or secondary containment boundary . Req requires that actions be immediately i nitiated to verify that each secondary containment pen                ation flow pat h is isolated or to verify that it can be manually isolated from the control room.          Examples of manual isolation from the control room cou l d include the use of manual isolation pushbuttons , control switches , or placing a sufficient number of radiation monitor channels in trip . A secondary containment penetration flow path can be considered isolated Required Actions D.2, when one barrier in the flow path is in place. Examples of D .3, and D.4 are    suitable barriers include , but are not limited to , a closed considered to be met  secondary containment isolation damper (SCIO) , a closed manual valve , a blind flange , or another sealing device that when secondary        sufficiently seals the penetration flow path . The primary containment,          containment upper personnel airlock and other primary secondary containment containment penetrations that bypass secondary containment penetrations, and the are considered part of the secondary containment boundary ;
Note that Required Actions D. 1, D. 2, D.3,
therefore , they must be considered when completing this Standby Gas Treatment action .
System are OPERABLE in          One SGT subsystem is capable of maintaining the secondary accordance with      containment at a negative pressure with respect to the environment and filter gaseous releases . Required Action LCO 3.6.4.1, LCO      0 . 4 requires that actions be immediately initiated to verify 3.6.4.2 , and LCO    that at least one SGT subsystem is capable of being placed 3.6.4.3.              in operation . The required verification is an administrative activity and does not require manipulation or testing of equipment .
(co ntinued )
CLINTON                              B 3 . 5 - 22                  Revision No . G-=6
 
RPV Wate r Inventory Control B 3.5.2 BASES AC TIONS        E.1 (continued}
If the Required Actions and associated Completion times of Conditions C or D are not met or if the DRAIN TIME is less than 1 hour , actions must be initiated immediately to restore the DRAIN TIME to 2 36 hours .               In this condi t ion ,
there may be insufficient time to respond to an unexpected draining event to prevent the RPV water inventory from reaching the TAF. Note that Required Actions D. 1 , D. 2 , D.3 ,
and D.4 are also applicable when DRAIN TIME is less t han 1 hour.
and D.4 are also applicable when DRAIN TIME is less t han 1 hour.
SURVEILLANCE    SR     3. 5 .2 . 1 REQUIREMENTS This Surveillance verifies that the DRAIN TIME of RPV water inventory to the TAF is 2 36 hours.               The period of 36 hours is considered reasonable to identify and initiate ac t ion to mitigate draining of reactor coolant . Loss of RPV water inventory that would result in the RPV wa t er level reaching the TAF in greater than 36 hours does not represent a significant challenge to Safety Limit 2 . 1 . 1 . 3 and can be managed as part of normal plant operation .
SR
: 3. 5.2. 1 This Surveillance verifies that the DRAIN TIME of RPV water inventory to the TAF is 2 36 hours.
The period of 36 hours is considered reasonable to identify and initiate act ion to mitigate draining of reactor coolant.
Loss of RPV water inventory that would result in the RPV wat er level reaching the TAF in greater than 36 hours does not represent a significant challenge to Safety Limit 2. 1. 1. 3 and can be managed as part of normal plant operation.
The definition of DRAIN TIME states that realistic cross -
The definition of DRAIN TIME states that realistic cross -
sectional areas and drain rates are used in the calculation .
sectional areas and drain rates are used in the calculation.
A realistic drain rate may be determined using a single ,
A realistic drain rate may be determined using a single,
s t ep - wise , or integrated calculation considering the changing RPV water level during a draining event . For a Control Rod RPV penetration flow path with the Control Rod Drive Mechanism removed and not replaced with a blan k flange , the realistic cross - sectional area is based on the control rod blade seated in the control rod guide tube.                         If the control rod blade will be raised from the penetration to adjust or verify seating of the blade , the exposed cross -
s t ep-wise, or integrated calculation considering the changing RPV water level during a draining event.
sectional area of the RPV penetration flow path is used .
For a Control Rod RPV penetration flow path with the Control Rod Drive Mechanism removed and not replaced with a blan k flange, the realistic cross - sectional area is based on the control rod blade seated in the control rod guide tube.
The definition of DRAIN TIME excludes from the calculation those penetration flow paths connected to an intact closed closed and                system , or isolated by manual or automatic valves that are administratively          lggJrnd ,   sealed , e.+/-:- gtJ::ierFise semued -i+l- .tfi.e Gl esed i;w sit i eH ,
If the control rod blade will be raised from the penetration to adjust or verify seating of the blade, the exposed cross -
controlled                blank flanges , or other devices that prevent flow of reactor coolant through the penetration flow paths . A blank flange or other bolted device must be connected with a sufficient number of bolts to prevent draining -i+l- .tfi.e ~ ~ e.++
sectional area of the RPV penetration flow path is used.
OperatiHg E-a-&i-& Earthg+iake .         Normal or expected leakage from closed systems or past isolation devices is permitted .
The definition of DRAIN TIME excludes from the calculation those penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are lggJrnd, sealed, e.+/-:- gtJ::ierFise semued -i+l-.tfi.e Gl esed i;w sit i eH,
Determination that a system is intact and closed or isolated must consider the status of branch lines .a.HG eHgeiHg p-l.a.H.t.
blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths.
ma iHt eH3. H8 e .a.HG t es tiH g a Gti uiti es .
A blank flange or other bolted device must be connected with a sufficient number of bolts to prevent draining -i+l-.tfi.e ~  
The Residual Heat Removal (RHR} Shutdown Cooling Sys t em is only considered an intact closed system when misalignment (continued}
~ e.++
CLINTON                                  B 3 . 5 - 23                       Rev i sion No . ~
OperatiHg E-a-&i-& Earthg+iake.
Normal or expected leakage from closed systems or past isolation devices is permitted.
Determination that a system is intact and closed or isolated must consider the status of branch lines.a.HG eHgeiHg p-l.a.H.t.
maiHteH3.H8 e.a.HG t es tiHg a Gtiuities.
The Residual Heat Removal (RHR} Shutdown Cooling Syst em is only considered an intact closed system when misalignment (continued}
B 3. 5-23 Revi sion No. ~  


RPV Water Inventory Control B 3.5.2 BASES SURVEILLANCE                 SR           3.5 . 2 . 1             (continued)
BASES SURVEILLANCE REQUIREMENTS SR 3.5. 2. 1 (continued)
REQUIREMENTS issues (Reference 6) have been precluded by functional valve inter l ocks or by isola                               *                      *
RPV Water Inventory Control B 3. 5. 2 issues (Reference 6) have been precluded by functional valve interl ocks or by isola
* n of RPV water out of an RH path, Or multiple penetration flow RHR Shutdown Cooling s paths susceptible to a common closed system if its c mode failure,                                                     to Remote Shutdown , which .___ _ _ _ _ _ __,_ _ _ _ _ _ _ __. tion signals .                               ~
* n of RPV water out of an RH path, Or multiple penetration flow RHR Shutdown Cooling s paths susceptible to a common closed system if its c mode failure, Remote Shutdown, which.__ _______ _, ________ _.tion to signals.  
temporary alterations in                                                ~- ~
~  
The exclusion of penetration f l w ~ from the j.......J::ie.t..e..r:ri:LJ....I:i..a.!~*~ 9 n of DRAIN TIME         consider the pgtgntial support of maintenance effects                                                         m       .Q+/- initiating ~ .Q.f:l.
~-~
  ....--.!::::::==========~ -i-t.em.& guppgrting maint e n:rnc e a.00 t e gting (rigg ing ,
temporary alterations in The exclusion of penetration fl w ~
If reasonable controls are           scaffolding , temporary shielding , p i ping plugs , gnubb e r implemented to prevent                                               r                         u failu re G-f. such .i-t.em&
from the j.......J::ie.t..e..r:ri:LJ....I:i..a.!~*~9 n of DRAIN TIME consider the pgtgntial support of maintenance effects m  
  ,____ _ _ _ _ _ _ _ _ _ _____, ~ r e ettlt                                               ~ a   draining event from a closed system or between the RPV and the isolation device ,
.Q+/- initiating ~  
temporary                            pgngtratign .f..l.g.w p.a..t.A ~ f:l..9.t. w gxcl g;lgg ~ ~       1 alterations from                      ~ calc11latign .
.Q.f:l.  
causing Surveillance Requirement 3 . 0 . 1 requires SRs to be m between performances . Therefore , any changes in pl the effect of the temporary              conditions that would change the DRAIN TIME require alterations on DRAIN TIME                new DRAIN TIME be determined .
....--.!::::::==========~ -i-t.em.& guppgrting mainte n:rnce a.00 t e gting (rigging,
need not be considered.
If reasonable controls are scaffolding, temporary shielding, p i ping plugs, gnubbe r implemented to prevent r
The Surveillance Frequency is controlled under the Reasonable controls                      Surveillance Frequency Control Program .
u failu re G-f. such.i-t.em&  
include, but are not limited to controls consistent with SR 3 . 5 . 2 . 2 and SR 3 . 5 . 2 . 3 the guidance in NUMARC 93-01, "Industry Guideline                The minimum water level of 12 ft 8 inches required or the suppression pool is periodically verified to ensure that the for Monitoring the                        suppression pool will provide adequate net positive suction Effectiveness of                        head (NPSH) for the ECCS pump , recirculation volume , and Maintenance at Nuclear                  vortex prevention . With the suppression pool water level less than the required limit, the required ECCS Power Plants," Revision4,                injection/spray subsystem is inoperable unless it is aligned N UMARC 91-06,                            to an OPERABLE RCIC storage tank.
,___ ___________ ____, ~
"Guidelines for Industry With regard to suppression pool water level values obtained Actions to Assess                        pursuant to this SR , as read from plant indicat i on Shutdown Management," or                  instrumentation , t he specified limit is not considered to be a nominal va lu e with respect to instrument uncertainties.
r e ettlt  
commitments to This requires additional margin to be added to the limit to NUREG-0612, "Control of                  compensate for instrument uncertainties , for implementation Heavy Loads at Nuclear                    in the associated plant procedures (Ref. 2).
~
Power Plants."                          When the suppression pool level is < 1 2 f t 8 inches , the HPCS System is considered OPERABLE only if it can take suction from the RCIC storage tank and the RCIC storage tank (co n tinued)
a draining event from a closed temporary alterations from causing the effect of the temporary alterations on DRAIN TIME need not be considered.
CLINTON                                                              B 3 . 5 - 24                 Rev i sion No .   ~
Reasonable controls include, but are not limited to controls consistent with the guidance in NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision4, N UMARC 91-06, "Guidelines for Industry Actions to Assess Shutdown Management," or commitments to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants."
CLINTON system or between the RPV and the isolation device,
pgngtratign.f..l.g.w p.a..t.A ~
f:l..9.t. w gxcl 1 g;lgg ~  
~  
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calc11latign.
Surveillance Requirement 3. 0. 1 requires SRs to be m between performances.
Therefore, any changes in pl conditions that would change the DRAIN TIME require new DRAIN TIME be determined.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3. 5. 2. 2 and SR 3. 5. 2. 3 The minimum water level of 12 ft 8 inches required or the suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for the ECCS pump, recirculation volume, and vortex prevention.
With the suppression pool water level less than the required limit, the required ECCS injection/spray subsystem is inoperable unless it is aligned to an OPERABLE RCIC storage tank.
With regard to suppression pool water level values obtained pursuant to this SR, as read from plant indicat i on instrumentation, t he specified limit is not considered to be a nominal value with respect to instrument uncertainties.
This requires additional margin to be added to the limit to compensate for instrument uncertainties, for implementation in the associated plant procedures (Ref. 2).
When the suppression pool level is < 12 f t 8 inches, the HPCS System is considered OPERABLE only if it can take suction from the RCIC storage tank and the RCIC storage tank (continued)
B 3. 5-24 Revi sion No. ~  


AC Sources -     Shu tdown B 3.8.2 the ability to BASES                                                                                            manually start a LCO                                        e l ectrical power s u pport , assuming a loss of the o fsite (continued )                            circui t .     Simi l arly , when the high pressure core s ray (HPCS ) is required to be OPERABLE , a separate offs ' te circui t to the Di vision 3 Class lE onsite electr i c l power distribution subsystem , or an OPERABLE Division 3 G, ensure an add i t i ona l sou r ce o f powe r f o r the HPCS . Toget e r ,
BASES LCO (continued)
OPERABI L ITY of the required offsite c i rcuit (s ) an DG (s )
AC Sources -
ll.5e::..!n.!s~u~res:.:::Su---:;:)'il" 9 Aatt:r 9 the availability o f s u fficient AC sources to operate the p l ant in a safe manner and to mitigate the consequences of pos t ulated events during shutdown (e . g ., fue l handling accidents ) .
Shutdown B 3. 8. 2 the ability to manually start a e l ectrical power s upport, assuming a loss of the o fsite circuit.
The qualified offsite circu i t ( s ) must be capable of maintaining rated frequency and vo l tage whi l e connec t ed to their respective ESF bus (es ) , and accepting required loads during an acciden t.           Qualif i ed offsite circuits are t h ose that are described in the USAR and are part of t he licens i ng basis for the plant . The offsite circuit consists of incoming breaker and disconnect to the respective reserve auxiliary transformer (RAT) or emergency reserve auxiliary t r ans f o r mer (ERAT ) , and the respect i ve c ir cu i t pat h including feeder breakers t o all 4 . 16 kV ESF buses required by LCO 3 . 8 . 10 . I n addition , an onsite , permanent l y insta l led static VAR compensator (SVC ) is availab l e for connec t ion to the offsite c i rcuits to s u pport required vol t age for t h e ESF b u sses . Connect i on of the SVC to the offsite circuit i s via circuit breakers to t h e secondary side of the RAT and/or ERAT .
Simi l arly, when the high pressure core s ray (HPCS ) is required to be OPERABLE, a separate offs ' te circuit to the Di vision 3 Class lE onsite electri c l power distribution subsystem, or an OPERABLE Division 3 G, ensure an addi t i ona l sour ce o f powe r f o r the HPCS.
Connec t ion and operation of the SVC ( s ) is dictated by the existing need for voltage sup port of t he offsite electrical power source ( s ) based on prevailing grid conditions . Thus ,
Toget e r,
OPERABILITY of the offsite electrica l power source (s ) is norma l ly supported by , but i s not necessari l y dependent on ,
OPERABI LITY of the required offsite c i rcuit (s ) an DG (s )
connection and operation of the SVC ( s ).           Th e resu l tant i mpact on OPERABI LI TY of t h e offs i te e l ect ri ca l sou r ce (s )
ll.5e::..!n.!s~u~res:.:::Su---:;:)'il" 9 Aatt:r 9 the availability o f s ufficient AC sources to operate the p l ant in a safe manner and to mitigate the consequences of pos t ulated events during shutdown (e. g., fue l handling accidents ).
CLINTON The qualified offsite circui t (s ) must be capable of maintaining rated frequency and vo l tage whi l e connect ed to their respective ESF bus (es ), and accepting required loads during an accident.
Qualifi ed offsite circuits are t hose that are described in the USAR and are part of t he licens i ng basis for the plant.
The offsite circuit consists of incoming breaker and disconnect to the respective reserve auxiliary transformer (RAT) or emergency reserve auxiliary t r ans f o r mer (ERAT ), and the respect i ve c ircui t path including feeder breakers t o all 4. 16 kV ESF buses required by LCO 3. 8. 10.
I n addition, an onsite, permanent l y instal led static VAR compensator (SVC ) is availab l e for connect ion to the offsite c i rcuits to s upport required vol t age for t he ESF busses.
Connecti on of the SVC to the offsite circuit i s via circuit breakers to t he secondary side of the RAT and/or ERAT.
Connect ion and operation of the SVC (s ) is dictated by the existing need for voltage support of t he offsite electrical power source (s ) based on prevailing grid conditions.
Thus,
OPERABILITY of the offsite electrical power source (s ) is norma l ly supported by, but i s not necessari l y dependent on,
connection and operation of the SVC (s ).
The resu l tant i mpact on OPERABI LI TY of t he offs i te e l ectrical sour ce (s )
from disconnecting the SVC (s ) from the offsite circuit (s )
from disconnecting the SVC (s ) from the offsite circuit (s )
can be determined by analysis b ased on u se of an established model of the o f fsite transm i ssion network and existing grid conditions , including availabl e generating sources , which can be u p dated on a dai l y or more frequen t bas i s . The mode l provides the capability to predict or determine what the onsite voltages would be at the RAT and/or ERAT (while connected to the offsite electrical sources ) under maximum postu l ated load conditions .
can be determined by analysis based on u se of an established model of the o f fsite transmi ssion network and existing grid conditions, including available generating sources, which can be updated on a dai l y or more frequen t bas i s.
(co n tinued )
The mode l provides the capability to predict or determine what the onsite voltages would be at the RAT and/or ERAT (while connected to the offsite electrical sources ) under maximum postu l ated load conditions.
CLINTON                                                              B 3 . 8- 35                   Rev i sion No .   ~
(continued )
B 3. 8-35 Revi sion No. ~  


AC Sources~Shutdown B 3.8.2 being manually BASES started LCO            The required DG mu st be capable of etartiHg , accelerating to (continued )  rated speed and vo l tage , and connect i ng to its respective ESF bus ~ 9ete,-;ti9H Q..f. ~ tiA90P ' 91Lige , and accepting required loads. ~ 2:Qr;;_{PQAQQ ffit.1-8-t- b. :;i,-;,-;gmp l igl:J.gg Hitl:l. i H
BASES LCO (continued)
                -+/-- 2:8Q9Hda       EaGR- JdG ffit.1-8-t- a-l-8-G- be- ,-;apablg Q..f. a,-;,-;eptiHg r eqti ire9 ~ u i tl:l. i A -t-RB- aggi;ime9 l oa9 i Hg 2eqtieA>Je iHtOP' ale , 6-A-d ffit.1-8-t- >J9AtiAtie -t-9 gperate tl-H-t-i-l- gff2ite pG-We-r-
APPLICABILITY CLI NTON AC Sources~Shutdown B 3. 8. 2 being manually started The required DG must be capable of etartiHg, accelerating to rated speed and vo l tage, and connecti ng to its respective ESF bus ~ 9ete,-;ti9H Q..f. ~
                ~ ~ regtgre9 -t-9 -t-RB- ~ bi;ises                         ~ ,-;apabi l itieg .a-r                 reqi;iire9 -t-9 ~ m.t. .f..r.m .eo " ariety Q..f. iAitia l Q9A9iti9Ae ~
tiA90P'91Lige, and accepting required loads.  
                .a-g.+. JdG .H:+ ataA9by .w-i-t-l:+/- .t.J:+/-. @AgiAQ ~ 6-A-d JdG .H:+ ataH9by
~
                .w-i-t4+ .t-l:J..@ @HgiHe a..t; eimbi@Ht Q9A9iti9Aa               Additi9Aal JdG
2:Qr;;_{PQAQQ ffit.1-8-t-b. :;i,-;,-;gmpl igl:J.gg Hitl:l.i H  
                ,-;apabilitieg ffit.1-8-t- &!- dem9Aatrated -t-9 H\B-t- reqti i red
-+/-- 2:8Q9Hda EaGR-JdG ffit.1-8-t-a-l-8-G-be-,-;apablg Q..f. a,-;,-;eptiHg r eqtiire9 ~
                &#xa3;tiP' eillaA>Jeg , e--.-g-.-, ,-;apability Q..f. -t-RB- JdG -t-9 re " ert -t-9 staAdby 2tati;ig ~ -e>H ECC&#xa3;- 2igAal wh-i-1-e- gperatiAg .H:+ para l lel
u i tl:l.i A -t-RB-aggi;ime9 l oa9 i Hg 2eqtieA>Je iHtOP'ale, 6-A-d ffit.1-8-t- >J9AtiAtie -t-9 gperate tl-H-t-i-l-gff2ite pG-We-r-
                .t-e-s-t. ~
~  
~ regtgre9 -t-9 -t-RB- ~
bi;ises  
~  
,-;apabi l itieg.a-r reqi;iire9 -t-9 ~ m.t..f..r.m.eo " ariety Q..f. iAitial Q9A9iti9Ae ~  
.a-g.+.
JdG.H:+ ataA9by.w-i-t-l:+/-.t.J:+/-. @AgiAQ ~
6-A-d JdG.H:+ ataH9by  
.w-i-t4+.t-l:J..@ @HgiHe a..t; eimbi@Ht Q9A9iti9Aa Additi9Aal JdG  
,-;apabilitieg ffit.1-8-t-
&!- dem9Aatrated -t-9 H\\B-t-reqti i red  
&#xa3;tiP'eillaA>Jeg, e--.-g-.-,,-;apability Q..f. -t-RB-JdG -t-9 re" ert -t-9 staAdby 2tati;ig ~  
-e>H ECC&#xa3;- 2igAal wh-i-1-e-gperatiAg.H:+ paral lel  
.t-e-s-t. ~
Prgpgr geqneA>JiHg Q..f. l9a9a 1 iA>Jln9iAg trippiAg Q..f.
Prgpgr geqneA>JiHg Q..f. l9a9a 1 iA>Jln9iAg trippiAg Q..f.
AQAOaaeHtieil lgagg , .i..e. .eo reqi;iire9 ftiA>Jti9A ~ JdG Qpgg llJH I. ITY I t is acceptab l e for divis i ons to be cross t i ed during shutdown conditions , permitting a s i ng l e offsite power circuit to supply all required AC e l ectrica l power distribution subsystems . No fast transfer capabi l ity is required for o ff site circuits to be considered OPERABLE for this LCO .
AQAOaaeHtieil lgagg,  
As described in Applicable Safety Analyses , in the event of an accident during shutdown , the TS are designed to maintain the p l ant in a condition s u ch that, e&#xa5;ef+ :w-i-t-A, ~ siAgle faili;ire , the p l ant will not be in immediate difficulty .
.i..e..eo reqi;iire9 ftiA>Jti9A ~
APPLICABILITY  The AC sources required to be OPERABLE in MODES 4 and 5 and during movement of irradiated fuel assemblies i n the primary or secondary containment provide assurance that :
JdG Qpgg llJH I. ITY I t is acceptabl e for divis i ons to be cross t i ed during shutdown conditions, permitting a s i ngl e offsite power circuit to supply all required AC e l ectrical power distribution subsystems.
: a.       Systems that provide core cooling are ava i lable ;
No fast transfer capabi l ity is required for off site circuits to be considered OPERABLE for this LCO.
: b.       Systems needed to mitigate a fuel handling accident are availab l e ;
As described in Applicable Safety Analyses, in the event of an accident during shutdown, the TS are designed to maintain the p l ant in a condition s uch that, e&#xa5;ef+ :w-i-t-A, ~ siAgle faili;ire, the p l ant will not be in immediate difficulty.
(co n tinued )
The AC sources required to be OPERABLE in MODES 4 and 5 and during movement of irradiated fuel assemblies i n the primary or secondary containment provide assurance that :
CLI NTON                                    B 3 . 8- 36                               Rev i sion No . G-=6
a.
Systems that provide core cooling are ava i lable ;
b.
Systems needed to mitigate a fuel handling accident are availab l e ;
(continued )
B 3. 8-36 Revi sion No. G-=6  


AC  Sources ~ Shutdown B 3.8.2 BASES ACTIONS          C. 1     (continued )
BASES ACTIONS SURVEILLANCE REQUIREMENTS SR 3.8.1.7, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.15, SR 3.8.1.18, and SR 3.8.1.19 are not required to be met because DG start and load within a specified time and response on an offsite power or ECCS initiation signal is not required.
additional required AC source is inoperable , and power is s t ill supplied to HPCS , 72 ho u rs is a l lowed to restore the additional required AC source to OPERABLE .                 This is reasonab l e cons i der i ng HPCS will st ill pe r fo r m i ts funct i on ,
lwhich precludes REFERENCES CLINTON C. 1 (continued )
absent an additional sing l e failure .
AC Sources ~ Shutdown B 3. 8. 2 additional required AC source is inoperable, and power is s t ill supplied to HPCS, 72 hou rs is a l lowed to restore the additional required AC source to OPERABLE.
SURVEILLANCE      SR     3.8.2.1 REQUIREMENTS SR 3 . 8 . 2 . 1 requires the SRs from LCO 3 . 8 . 1 that are necessary for ensuring the OPERABILITY of the AC sources in SR 3.8 .1.7, SR o t her tha ~MODES 1 , 2 , and 3 .         SR 3 . 8.1 . 8 is not requ ired to 3.8.1.11, SR 3.8.1.12,  be met sin e only one offsite circuit is required to be SR 3.8.1.13, SR          OPERABLE .       In MODES 4 and 5 ECCS injection/spray subsystems 3.8 .1.15, SR 3.8 .1.18, are manually controlled in accordance with LCO 3 . 5 . 2 ,
This is reasonabl e cons i deri ng HPCS will still pe r fo r m i ts funct i on,
                            " Reactor Pressure Vesse l (RPV) Water I nventory Contro l." No and SR 3.8.1 .19 are ECCS initiation signals are credited for initiation of these not required to be met    subsystems . Adequate time is availab l e to manually start because DG start and    and load DGs from the Main Contro l Room in support of RPV load within a specified  inventory contro l, if required . Therefore , SR 3 . 8 . 1 . 12 and SR 3 . 8 . 1 . 19 , which verify the DG ' s capability to start time and response on automatically on actual or simulated ECCS init i ation an offsite power or      signa l s , are not required to be met i n MODES 4 and 5 .
absent an additional singl e failure.
ECCS initiation signal  SR 3 . 8 . 1 . 17 is not required to be met because the required is not required.        OPERABLE DG (s ) is not required to undergo periods of being synchronized to the offsite circuit .             SR 3 . 8 . 1.20 is excepted because starting i ndependence is not required with the DG ( s ) that is not required to be OPERABLE . Refer to the corresponding Bases for LCO 3 . 8 . 1 for a discussion of each lwhich precludes            <;: P' This SR is modified by a             Note~~ ~     reasgn
SR 3. 8. 2. 1 SR 3. 8. 2. 1 requires the SRs from LCO 3. 8. 1 that are necessary for ensuring the OPERABILITY of the AC sources in o t her tha~MODES 1, 2, and 3.
                          .t.G preclYde requiring the OPERABLE DG (s ) from being
SR 3. 8.1. 8 is not requ ired to be met sin e only one offsite circuit is required to be OPERABLE.
                                                                                      ~    .t.fte. ~~
In MODES 4 and 5 ECCS injection/spray subsystems are manually controlled in accordance with LCO 3. 5. 2,  
paral l eled with the offsite power network or otherwise rendered inoperable during the performance of SRs , and preclude de - energizing a required 4 .1 6 kV ESF bus or disconnecting a requ ired offsite circuit during performance of SRs . With l imited AC sources available , a single event could compromise both the required circuit and the DG .                   It is the intent that these SRs must sti l l be capable of being met , but actua l performance is not required for any DG or offsite circuit .
"Reactor Pressure Vesse l (RPV) Water I nventory Control."
REFERENCES        None .
No ECCS initiation signals are credited for initiation of these subsystems.
CLINTON                                  B 3 . 8 - 39                       Rev i sion No . ~}}
Adequate time is availab l e to manually start and load DGs from the Main Control Room in support of RPV inventory control, if required.
Therefore, SR 3. 8. 1. 12 and SR 3. 8. 1. 19, which verify the DG ' s capability to start automatically on actual or simulated ECCS initi ation signal s, are not required to be met i n MODES 4 and 5.
SR 3. 8. 1. 17 is not required to be met because the required OPERABLE DG (s ) is not required to undergo periods of being synchronized to the offsite circuit.
SR 3. 8. 1.20 is excepted because starting i ndependence is not required with the DG (s ) that is not required to be OPERABLE.
Refer to the corresponding Bases for LCO 3. 8. 1 for a discussion of each  
<;: P' This SR is modified by a Note~~~
reasgn ~
.t.fte. ~
~
.t.G preclYde requiring the OPERABLE DG (s ) from being paral l eled with the offsite power network or otherwise rendered inoperable during the performance of SRs, and preclude de - energizing a required 4.1 6 kV ESF bus or disconnecting a requ ired offsite circuit during performance of SRs.
With l imited AC sources available, a single event could compromise both the required circuit and the DG.
I t is the intent that these SRs must sti l l be capable of being met, but actua l performance is not required for any DG or offsite circuit.
None.
B 3. 8-39 Revi sion No. ~}}

Latest revision as of 14:38, 29 November 2024

Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
ML20323A248
Person / Time
Site: Dresden, Clinton, Quad Cities, LaSalle  
Issue date: 11/18/2020
From: Simpson P
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML20324A090 List:
References
RS-20-115, TSTF-582
Download: ML20323A248 (85)
v • d • e


Text

4300 Winfield Road Warrenville, IL 60555 Exelon Generation RS-20-115 November 18, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 630 65 7 2000 Office Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 10 CFR 50.90

Subject:

Application to Revise Technical Specifications to Adopt TSTF-582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements"

References:

1. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0, 'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020
2. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0, 'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020

November 18, 2020 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRG-approved Industry/Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," (Reference 1 ), and also incorporates the variation described in Reference 2. provides a description and assessment of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change. Attachment 3 provides TS Bases pages marked up to show the associated TS Bases changes and is provided for information only.

The proposed change has been reviewed by the Plant Operations Review Committees at each station in accordance with the requirements of the EGC Quality Assurance Program.

EGC requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLllP). Approval of the proposed amendment is requested within six months of completion of the NRC's acceptance review. Once approved, the amendment shall be implemented within 60 days.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 18th day of November 2020.

Respectfully, Pa+/-tR~

Patrick R. Simpson Sr. Manager Licensing Attachments:

1. Description and Assessment
2. Markup of Proposed Technical Specifications Pages
3. Markup of Proposed Technical Specifications Bases Pages (For Information Only)

November 18, 2020 U.S. Nuclear Regulatory Commission Page 3 cc:

NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station (Dan Tesar)

Illinois Emergency Management Agency - Division of Nuclear Safety

1.0 DESCRIPTION

ATTACHMENT 1 Description and Assessment Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," which is an approved change to the Improved Standard Technical Specifications (ISTS), into Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, Technical Specifications (TS). The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions in TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The proposed changes also include the variation described in TSTF-583 and discussed in Reference 3.

2.0 ASSESSMENT

2.1 Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a letter dated August 13, 2020 (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1 ). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.

EGC verified that the required ECCS injection/spray subsystem can be aligned and the pump started using relatively simple evolutions involving the manipulation of a small number of components. These actions can be performed in a short time (less than the minimum Drain Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) from the control room following plant procedures.

2.2 Variations 2.2.1 Proposed TS Changes to Adopt TSTF-583-T, "TSTF-582 Diesel Generator Variation" TSTF-582, "RPV WIC Enhancements," states:

The ECCS injection/spray subsystem required to be operable by LCO 3.5.2 must be capable of being manually started as defense-in-depth against an unexpected draining event. The changes in TSTF-542 did not assume automatic actuation of the ECCS subsystem. TS 3.5.2, Required Action D.1 requires an additional method of water injection and that the required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. However, LCO 3.5.2 does not assume that the onsite electrical power source will start automatically on an ECCS or loss of power signal.

Page 1

ATTACHMENT 1 Description and Assessment LCO 3.8.2, "AC Sources - Shutdown," requires one offsite circuit and one diesel generator to be operable in Modes 4 and 5. SR 3.8.2.1 lists the TS 3.8.1, "AC Sources -

Operating," SRs that are applicable in Modes 4 and 5. In an oversight in TSTF-542, the TS 3.8.1 SRs that test automatic start and loading of a diesel generator on an ECCS or loss of offsite power signal were not excluded from SR 3.8.2.1.

TSTF-582 revises Technical Specification (TS) 3.8.2, "AC Sources - Shutdown," Surveillance Requirement (SR) 3.8.2.1, to exclude SRs that verify the ability of the diesel generators to automatically start and load on an ECCS initiation signal or loss of offsite power signal.

The NRC Safety Evaluation for TSTF-582 (ADAMS Accession No. ML20223AOOO, dated, August 13, 2020), Section 3.6, "Alternating Current Sources - Shutdown, STS 3.8.2," states:

STS 3.5.2, "Reactor Pressure Vessel Water Inventory Control (RPV WIC)," does not require automatic ECCS initiation to mitigate a draining event in Modes 4 and 5, and the ECCS initiation signal related to the automatic ECCS initiation is removed from the STS.

Because the automatic ECCS initiation and related ECCS initial signal in Modes 4 and 5 are eliminated, the automatic start of the DG on an ECCS initiation signal is not required in Modes 4 and 5.... [T]he NRC staff finds that STS 3.5.2 provides enough time from the onset of the [loss of offsite power] LOOP event for the operator to manually start the DG required to supply power to the water injection equipment to mitigate the draining event in Modes 4 and 5. In addition, STS 3.5.2 does not require the automatic initiation of the ECCS injection/spray subsystem or the additional method of water injection. Therefore, since STS 3.5.2 allows enough time to manually start the DG and the equipment for water injection, the NRC staff finds that the automatic start and loading of the DG are not necessary on a LOOP signal or LOOP concurrent with an ECCS initiation signal to mitigate a draining event in Modes 4 and 5.

Furthermore, the NRC staff notes that other events postulated in Modes 4 and 5 (e.g.,

FHA, waste gas tank rupture) and during movement of [recently] irradiated fuel assemblies in the [primary and secondary containment] do not assume a LOOP event or an automatic ECCS initiation.

TSTF-582 did not include all of the TS changes needed to reflect that TS 3.8.2 should not require automatic start and loading of a diesel generator within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities) on an ECCS initiation signal or a loss of offsite power signal.

TS 3.3.8.1, "Loss of Power (LOP) Instrumentation," is applicable in Modes 1, 2, and 3, and when the associated diesel generator is required to be operable by TS 3.8.2. TSTF-582 revised TS 3.8.2 to no longer require automatic start and loading of a diesel generator on a loss of offsite power signal. Consequently, the LOP instrumentation that generates the loss of offsite power signal should not be required to be operable when the diesel generator is required to be operable by TS 3.8.2. The Applicability of LCO 3.3.8.1 is revised to not include the specified condition "When the associated diesel generator is required to be OPERABLE by LCO 3.8.2, 'AC Sources - Shutdown'."

Page 2

ATTACHMENT 1 Description and Assessment TS SR 3.8.1.7 and SR 3.8.1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), require that the DG starts from standby or hot conditions, respectively, and achieve required voltage and frequency within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities). The 12 to 13 second start requirement supports the assumptions in the design basis LOCA analysis.

This capability is not required during a manual diesel generator start to respond to a draining event, which has a minimum Drain Time of one hour. Therefore, SR 3.8.1.7 and SR 3.8.1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), are added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.

These SRs are not included under SR 3.8.2.1.

Clinton, Dresden, and Quad Cities TS SR 3.8.1.18 state "Verify interval between each sequenced load block is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed. The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1 LaSalle TS SR 3.8.1.18 state "Verify interval between each sequenced load block, for Division 1 and 2 DGs only, is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed. The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1 The TS 3.8.2 LCO Bases were not updated by TSTF-542 or TSTF-582 to reflect that automatic start and loading of a diesel generator is not required. The LCO 3.8.2 and SR 3.8.2.1 Bases are revised to reflect the TS requirements.

This variation provides consistency within the TS after incorporating the TSTF-582 changes to SR 3.8.2.1.

As an editorial improvement, SR 3.8.2.1 is revised to list the TS 3.8.1 SRs that are applicable instead of listing the TS 3.8.1 SRs that are not applicable. The SR 3.8.2.1 Bases are not affected and explain why the omitted TS 3.8.1 SRs are not applicable to TS 3.8.2.

Page 3

2.2.2 Editorial Variations ATTACHMENT 1 Description and Assessment The Clinton, Dresden, LaSalle, and Quad Cities TS utilize different numbering and titles than the Standard Technical Specifications on which TSTF-582 and TSTF-583-T were based. Table 1 describes the differences between the plant-specific TS numbering and titles and the TSTF-582 and TSTF-583T numbering and titles. These differences are administrative and do not affect the applicability of TSTF-582 to these plant's TS.

Table 1. TSTF-582 and TSTF-583-T BWR4 and BWRG Numbering and Title Variations TSTF-582 (BWR4)

Dresden Quad Cities Table 3.3.5.2-1 Table 3.3.5.2 System Table 3.3.5.2 System RHR System Isolation nomenclature difference nomenclature difference Shutdown Cooling RHR Shutdown Cooling System (SOC) Isolation System (SOC) Isolation SR 3.5.2.5 Numbering difference Numbering difference SR 3.5.2.4 SR 3.5.2.4 -

SR 3.5.2.7 Numbering difference Numbering difference SR 3.5.2.6 -

SR 3.5.2.6 TS 3.6.1.3 Condition F Numbering difference Numbering difference TS 3.6.1.3 Condition E -

TS 3.6.1.3 Condition E TSTF-583-T (BWR4)

Dresden Quad Cities SR 3.8.1.9 Numbering difference Numbering difference SR3.8.1.10 SR 3.8.1.10 SR3.8.1.10 Numbering difference Numbering difference SR 3.8.1.11 SR 3.8.1.11 SR3.8.1.14 Numbering difference Numbering difference SR3.8.1.15 SR 3.8.1.15 SR3.8.1.16 Numbering difference Numbering difference SR3.8.1.17 SR 3.8.1.17 TSTF-582 (BWR6)

Clinton LaSalle Table 3.3.5.2-1 N/A System nomenclature RHR System Isolation difference RHR Shutdown Cooling System Isolation TS 3.3.6.1 Required Action Numbering difference N/A J.2 TS 3.3.6.1 Required Action M.2 Page4

2.2.3 Other Variations ATTACHMENT 1 Description and Assessment 2.2.3.1 Clinton, Dresden, LaSalle, and Quad Cities Additional Variations EGC is proposing the following additional variations from the TS changes described in TSTF-582. The variations are described in Table 2. These variations do not affect the applicability of TSTF-582 to the proposed license amendments.

Table 2. TSTF-582 BWR4 and BWRG Other Variations TSTF-582 (BWR4)

Dresden Quad Cities Comments SR 3.3.5.2.3 No equivalent SR No equivalent SR No changes made TS 3.6.1.3 Condition G No equivalent No equivalent No changes made condition condition TS 3.6.1.3 Condition H No equivalent No equivalent No changes made condition condition TSTF-582 (BWR6)

Clinton LaSalle Comments TS 3.3.5.2 Conditions D No equivalent No equivalent No changes made and E Condition E Conditions D and E SR 3.3.5.2.3 No equivalent SR No equivalent SR No changes made SR 3.5.2.7 No equivalent SR N/A No changes made 2.2.3.2 Clinton Specific Variation EGC is proposing the following variations from the TS changes described in TSTF-582 for Clinton Power Station. EGC is proposing to delete TS 3.3.6.1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4. These are not included in TSTF-582. With the TSTF-582 deletion of TS 3.3.6.1 M.2 for Clinton (J.2 in TSTF-582), TS 3.3.6. 1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 are no longer applicable. These Clinton specific actions are no longer applicable after adoption of TSTF-542 (Reference 5, 6, and 7). Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 should be deleted with the deletion of TS 3.3.6.1 M.2. This plant specific variation does not impact the applicability of TSTF-582 to the Clinton TS.

Page 5

ATTACHMENT 1 Description and Assessment

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Analysis Exelon Generation Company, LLC (EGC), requests adoption of TSTF 582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements." The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." TSTF-582 includes the following changes to the TS:

1. The Drain Time definition is revised to move the examples of common mode failure mechanisms to the Bases and seismic events are no longer considered a common mode failure mechanism.
2. The Drain Time definition exception from considering the Drain Time for penetration flow paths isolated with manual or automatic valves that are "locked, sealed, or otherwise secured" is revised to apply the exception for manual or automatic valves that are "closed and administratively controlled."
3. The TS are revised to permit placing an inoperable isolation channel in trip as an alternative to declaring the associated penetration flow path incapable of automatic isolation.
4. A Surveillance Requirement (SR) that requires operating the required Emergency Core Cooling System (ECCS) injection/spray subsystem for at least 10 minutes through the recirculation line, is modified to permit crediting normal operation of the system to satisfy the SR and to permit operation through the test return line.
5. Dresden, Unit 2 and 3 share secondary containment structures between units. LaSalle, Unit 1 and 2 share secondary containment structures between units. Quad Cities, Unit 1 and 2 share secondary containment structures between units. The TS Actions are revised to recognize that an operable secondary containment and operable secondary containment isolation valves satisfy the Required Actions.
6. The Clinton, Dresden, LaSalle, and Quad Cities designs contain additional isolation instrumentation functions based on low RPV water level that could be credited when calculating Drain Time. Those functions are added to the required functions in TS 3.3.5.2.
7. TS 3.8.2, "AC Sources - Shutdown," SR 3.8.2.1, is revised to not require SRs that test the ability of the automatic diesel generator to start in Modes 4 and 5. Automatic ECCS Page 6

ATTACHMENT 1 Description and Assessment initiation in Modes 4 and 5 was eliminated in TSTF-542. This was an oversight in TSTF-542.

8. TS 3.3.6.1, "Primary Containment Isolation Instrumentation," Required Action J.2 (J.2 for LaSalle and M.2 for Clinton) is deleted. This action is no longer applicable after adoption of TSTF-542. This was an accidental omission in TSTF-542. This change is made for clarity and has no effect on the application of the TS.
9. The Applicability of TS 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," is revised to delete the phrase, "When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, 'Primary Containment Isolation Instrumentation'." This makes TS 3.6.1.3 only applicable Modes 1, 2, and 3. Following adoption of TSTF-542, no functions in LCO 3.3.6.1 are applicable outside of Modes 1, 2, or 3. The Actions and SRs are revised to reflect this change. These changes are made for clarity and have no effect on the application of the TS.
10. The TS are revised to use wording and to define acronyms in a manner consistent with the remainder of the TS. These changes are made for consistency and have no effect on the application of the TS.

EGC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1.

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." Draining of RPV water inventory in Mode 4 (i.e., cold shutdown) and Mode 5 (i.e., refueling) is not an accident previously evaluated and, therefore, revising the existing TS controls to prevent or mitigate such an event has no effect on any accident previously evaluated. RPV water inventory control in Mode 4 or Mode 5 is not an initiator of any accident previously evaluated. The existing and revised TS controls are not mitigating actions assumed in any accident previously evaluated.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Page 7

ATTACHMENT 1 Description and Assessment

2.

Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?

Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The event of concern under the current requirements and the proposed change is an unexpected draining event. The TS have contained requirements related to an unexpected draining event during shutdown for over 40 years and this event does not appear as an analyzed event in the Updated Final Safety Analysis Report (UFSAR) for any plant or in the NRC's Standard Review Plan (NUREG- 0800). Therefore, an unexpected draining event is not a new or different kind of accident not considered in the design and licensing bases that would have been considered a design basis accident in the UFSAR had it been previously identified.

None of the equipment affected by the proposed change has a design function described in the UFSAR to mitigate an unexpected draining event in Modes 4 or 5, although the equipment may be used for that purpose. Therefore, the proposed amendment will not change the design function of the affected equipment. The proposed change will affect the operation of certain equipment, such as the manual initiation function and related instrumentation to permit initiation of the required ECCS injection/spray subsystem, and the control of valves credited for preventing a draining event. However, these changes provide adequate protection to prevent or mitigate an unexpected draining event and do not create the possibility of a new or different kind of accident due to credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed change involve a significant reduction in a margin of safety?

Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The safety basis for the RPV WIC requirements is to protect Safety Limit 2.1.1.3. The proposed change does not affect any specific values that define a safety margin as established in the licensing basis. The proposed change does not affect a design basis or safety limit, or any controlling value for a parameter established in the UFSAR or the license.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Page 8

ATTACHMENT 1 Description and Assessment Based on the above, EGC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4.0 ENVIRONMENTAL CONSIDERATION

The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

5.0 REFERENCES

1. Letter from the Technical Specifications Task Force to the U.S. Nuclear Regulatory Commission, "Transmittal of TSTF-582, Revision 0, RPV WIC Enhancements,"' dated August28, 2019
2. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,

'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020

3. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,

'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020

4. NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 4, dated April 2012 Page 9

ATTACHMENT 1 Description and Assessment

5. NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants, Volume 1, Revision 4, dated April 2012
6. Letter from Alexander R. Klein (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control," dated December 20, 2016
7. Letter from P. Simpson (EGC) to U.S. NRC, "Application to Revise Technical Specifications Following Adoption of TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,"' dated June 18, 2019 Page 10

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 1.0-3 1.0-4 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-51 3.3-52 3.3-78 3.8-19

Definitions 1.1 1.1 Definitions (continued)

CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT I - 131 DRAIN TIME CLINTON The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each re l oad cycle in accordance with Specification 5. 6. 5.

Plant operation within these limits is addressed in individual Specifications.

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.

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 I

8ei8mic e uent,.l.B-8-& M normal po 1 1er, Bingle R-Yma-n error ), for all (continued) 1.0- 3 Amendment No. ~

Definitions DRAIN TIME (continued)

EMERGENCY CORE COOLING SYSTEM (ECCS ) RESPONSE TIME CLINTON Definitions

1. 1 closed and administratively controlled penetrati on flow paths below the TAF except 1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic va l ves that are l ocked, sea l ed,

G-t-otheri1ise secured in the closed position, b l ank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths ;

2.

Penetration flow paths capable of being isolated by va l ves that will c l ose automatical l y without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water l evel isolation instrumentati on ; or 3.

Penetration flow paths with iso l ation 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 t h e control room, is stationed at the controls, and is capab l e of closing the penetration flow path i solation devices without offs i te power.

c.

The penetration f l ow 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 addit i onal draining events occur ; and e.

Realistic cross - sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in l ieu of a ca l culated va l ue.

The ECCS RESPONSE TIME shall be that time i nterval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until t he ECCS equipment is capable of performing its safety function (i. e., the valves travel to t heir 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 seri es of sequential,

over l app i ng, or total steps so t hat the entire response time is measured.

(continued )

1.0- 4 Amendment No. ~

3. 3 INSTRUMENTATION RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 3. 3. 5. 2 Reactor Pressure Vesse l (RPV ) Water I nventory Control I nstrumentation LCO 3. 3. 5. 2 The RPV Water I nventory Control instrumentation for each Function in Table 3. 3. 5. 2-1 shall be OPERABLE.

APPLICABIL I TY :

According to Tab l e 3. 3. 5. 2-1.

ACTIONS

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

Separate Condition entry is al l owed for each channel.

CONDITION A...-

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~

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Decl a r e associated penet r ation flow path (s ) incapable of automat i c isolation.

Initiate action to calcul ate DRAIN TIME.

3. 3-43a COMPLETION TIME Immediately Immedi ately Immediately (continued )

Amendment No. J.;b.

ACTIONS (conti nued )

CONDITION

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These SRs apply to each Function in RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 SURVE I LLANCE REQUIREMENTS

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

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SURVEILLANCE SR 3. 3. 5. 2.l Perform CHANNEL CHECK.

SR 3. 3. 5. 2. 2 Perform CHANNEL FUNCT I ONAL TEST.

CLINTON 3. 3-43c FREQUENCY I n accordance wi th t he Surveil l ance Frequency Control Program In accordance with the Surveil l ance Frequency Control Program Amendment No. ~

FUNCTION.-

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RPV Water Inventory Contro l Instrumentat i on 3. 3. 5. 2 Table 3. 3. 5. 2-1 (page 1 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE CQNPITIQ11£ MODES OR REQUIRED l<li!:Fl!:l<l!:llC!W OTHER CHANNELS ERGM SPECIFIED PER l<l!:Ql!Il<l!:P

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ALLOWABLE CONDITIONS FUNCTION

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b91' (llypns )

RHR System Isolation a.

Reactor Vessel Water Level -

Low, Level 3 Reactor Water Cleanup (RWCU) System Isolation a.

Reactor Vessel Water Level -

Low Low, Level 2 RPV Water Inventory Control Instrumentati on 3. 3. 5. 2 Table 3. 3. 5. 2 - 1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4 <b1, a*

(<> )

~

(<> )

REQUIRED CHANNELS PER FUNCTION 2 in one trip system 2 in one trip system CQNblITIQN£ Fli:Fli:Rli'.NCIW

-FRGM Fli:QTJIF!i:bl JlCTIQN Jl 1

£TlF" li:IbPNC!i:

Fli:QTJIF!i:Nli:NT£

.£R

-a-]~]"""-'~2>-.-+/--

1

.£R

-a-]~]"""-'~2~

2

.£R

~:;~:;_...,.'"'"""2~1

.£R

] -.--a

]-.-d~2,.....-.=-

2 2 1 2 1 2 1 ALLOWABLE VALUE

~ ?QQ gpm

". 8.3 inches
". - 48. 1 inches

+a+

" ssssi3te9 11itl=l aA Rccg s11ssyste111 ret=J:11ireol ts loe QP!i:F " llbli: loy bCQ :; 3 2,

" FP" Water IA"eAte;sy C9Atrgl "

Wl=leA MPcg is QP!i:F " llbli: fgr G9111pliaAGe 11itl=l bCQ :; 3 2,

" FP" Water IA" eAtsry C9Atrsl, " aA9 aligAeol ts tl=le FCIC stsrage taAk 'll=lile taAk *1ater level is Ast 11itl=liA tl=le limits gf

£F ] a 2 ]

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

CLINTON 3.3-44 Amendment No. ~

Primary Containment and Drywell Isolation Instrumentation 3. 3. 6. 1 ACTIONS (continued)

J.

K.

L.

M.

CONDITION As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.

As required by Required Action F. l and referenced in Table 3. 3. 6.1 - 1.

OR Required Act i on and associated Completion Time of Condition I or J not met.

As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.

As required by Required Action F. l and referenced in Table 3. 3. 6. 1-1.

CLINTON J. l K. l AND K. 2 L. l OR L. 2 M. l REQUIRED ACTION Isolate the affected penetration flow path (s).

Be in MODE 3.

Be in MODE 4.

Declare associated standby liquid control subsystem inoperable.

Isolate the Reactor Water Cleanup System.

Initiate action to restore channel to OPERABLE status.

IHitiate aGtiGH.t4 isGlate ~

1;:es i cilnl

~

1;:e1+18a l ~

£l::wtciGHH CGGliHg

£ystem snGtiGH ~

~

re21GtGr "essel 3.3-51 COMPLETION TIME 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 /> 1 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Immediately Immeciiately (continued)

Amendment No. ~

Primary Containment and Drywell Isolation Instrumentation 3. 3. 6. 1 ACTIONS M.

N.

CONDITION (Continued)

As required by Required Action F. l and referenced in Table 3. 3. 6. 1 - 1.

CLINTON REQUIRED ACTION Initiatg aQtign.t4 rgstgrg SQQgndary Qgnt;;iinmgnt.t4 QPJi:'.RAJ3I.E: steitns Initiatg aQtign.t4 r gstgrg ' standay ga.& trgatmgnt ~

s 11agyst:gm.t4 QPE:RAJ3I.E:

status Initiatg aQtign.t4 rgstgrg isglatign Qapaaility.i.A ~

r9b{ 11 irgd SQQgnd;;iry Qgntainmgnt 6-00 s g Qgndary Qgntainmgnt aypass p g n g tratign

~

pa-th A-G-t-is g lat 9 d M.--J-. NQ TE:

N. 1 OR N. 2 E+l-t-Pf aH-G ~

-i-&

pgrmissiblg.um:ie-r-administratiug Qm:1trgl Initiatg aQtign.t4

-G-1-G-&e- '

OOG-r-.i.A -t-fi.e-

.uppe-r. Qgntainmgnt pgrsgnngl d-i+/-- ~

Isolate the affected penetration flow path (s).

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

3.3-52 COMPLETION TIME Immgdiatg ly Immediately Immediately Amendment No. ---2-1-e.

3. 3 I NSTRUMENTATION 3. 3. 8. 1 Loss of Power (LOP ) Instrumentation LOP Instrumentati on 3. 3. 8. 1 LCO 3. 3. 8. 1 The LOP i nstrumentation for each Function in Tab l e 3. 3. 8. 1-1 shal l be OPERABLE.

APPLICABIL I TY :

MODES 1, 2, and 3, ~

Wfi.e-A.:l;.l:i.e aeeocia.te d di e s e l ge n e ra.tor ~

.i.& r e qtJ.ire d.t.G b.e-OP:E;g7\\fl1.8 b:f I.W ~ g

~

.'.!.AG £onrce s - £J:rntdoun "

ACTIONS

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

Separate Condition entry is al l owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A. 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 /> inoperable.

AND A. 2

NOTE----------

On l y applicable for Funct i ons 1. c, 1. d,

1. e, 2. c, 2. d, and 2. e Restore channel to OPERABLE statu s.

7 days B.

Required Act i on and B. l Declare associated DG Immediately associated Completion inoperable.

Ti me not met.

CLINTON 3.3-78 Amendment No. ~

AC Sources ~ S hu tdown 3. 8. 2 SURVE I LLANCE REQUIREMENTS SURVEILLANCE SR 3. 8. 2. l

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

The fol l owing SRs are not required to be.Jt:!

per f ormed :

SR 3.8. 1.3, SR 3. 8. 1.9 through

$R ~ g l ll, $R J g l u through SR 3. 8. 1. 16, 6-AG $R J g l a.

lowing SRs The fol are app

~

~

AC sources required to be OPERABLE~

licable for

£.R.g. ~ £pg,-;ifi£atioi:i J g l, gxggpt

$R ~ g l g, $R J g l 16, $R J g l 17 '

$R ~ g l lg, 6-AG $R J g l 6Q a-re appli.-;afile SR 3.8.1.1 SR 3.8.1.6 SR 3.8.1.2 SR 3.8.1.9 SR 3.8.1.3 SR 3.8.1.10 SR 3.8.1.4 SR 3.8.1.14 SR 3.8.1.5 SR 3.8.1.16 CLINTON 3. 8-19 FREQUENCY

~

, SR 3.8.1.10, SR 3.8.1.14, and

--0 I n accordance with appl i cable SRs Amendment No. ~

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.6.1.3-5 3.8.2-3

Definitions

1. 1 1.1 Definitions (continued)

DRAIN TIME closed and administratively controlled Dresden 2 and 3 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. §., seismic eveAt,

l oss of Aorrna l po*.1er, siA§le hbtrnaA error),

for all penetration flow paths below the TAF except:

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are l ocke9, sea l e9, or other* *i se seCb1re8 in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration fl ow 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 device without offsite power.

(continued) 1.1-4 Amendment No. 266/259

3.3 I NSTRUMENTATION RPV Water Inventory Contro l Instrumentation 3.3. 5. 2 3.3.5.2 Reactor Pressure Vesse l (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentation for each Funct i on in Table 3.3.5.2-1 sha l l be OP ERABLE.

AP PLI CAB ILITY:

According to Tab l e 3.3.5.2-1.

ACTIONS

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

A.On in ope Separate Cond i tion entry is al lowed for each channe l.

CON DIT ION REQU I RED AC TI ON COM PLETI ON TI ME A.-

GAe OF Arn Fe GAflAAe~ s A--.+/--

E:A teF tl:le 6oA9itioA I11m1e9i ete~ J' iAOFJeFaB~e Fef:eFeAGe9 i A

+a t:i~e J

. J

. a

. ~ 1 f:OF A.1 I tRe GAaAAe~

\\¥

.g.._

As Fe~tJiFe9 BJ'

.g....,..+

Initiate act i on to Immediately

\\

Re~tJi Fe9 AGtiOA A. 1 place channe l in a Ag Fef:eFeAGe9 i A trip.

+at:i ~e J

. J

. a

. ~ 1.

OR IA.2.1 I it e or more channels

~

Dec l are associated Immediately rable.

penetration fl ow path(s) incapable of automatic iso l ation.

A~

B.2. 2 Initiate action to Immediately ca l cu l ate DRAIN TIM E.

6. As Fe~tJi Fe9 gJ1 b----.----+/--

i:n aGe GAaAAe~ i A tFiFJ.

1 AOLiF Re~tJiFe9 AGtioA A. 1 fJA9 Fef:eFeAGe9 i A

+at:i~e J.J. a. 2 1.

(cont i nued)

Dresden 2 and 3 3.3.5. 2-1 Amendment No. 2§g/2§1

RPV Water Inventory Contro l Instrumentation 3.3. 5. 2 ACTIONS COND IT ION REQUIRED ACTION COMP LETI ON TI ME Q. As FeEjtii reEI B:J'

.IJ-.--+/-.

Restere GRannel te 24 R8blFS ReEjti ire El AGtien A. 1 OPrnAgLE stattis.

a nEI ref:erenGeEI in

+:a8le

~

. ~

. 9

. 2 1.

E. ReEjti ire El AGtien a nEI

-h IJeGlare asseGiateEI l ei,1

+/-mmeEli atel:J' asseGiateEI 6emf)letien flFesstire E66£

+:ime ef: 6enElitien 6 8F i naeGti en,LSfJFa:J' Q net met.

SblBS:J'Stem inef)eFa8le.

SURV EILLANCE REQUIR EMENTS

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

~These SRs apply to each Function in I

Ref:er te Tab l e 3.3.5.2-1 te Eletermine 11RiGR £Rs af)fllY f:er eaGR E66£

~tinGtien SURVEI LLANC E SR 3.3.5. 2.1 Perform CHANNE L CHECK.

SR 3.3.5.2.2 Perform CHANNE L FUNCTI ONAL TEST.

Dresden 2 and 3 3.3.5. 2-2 FREQUENCY In accordance with the Survei l lance Frequency Contro l Program In accordance wi t h the Survei l lance Frequency Contro l Program Amendment No. 268/261

FUNCTION

~ ReaGter Steam Geme Press~re be11 (Permissi,,e)

B-.

Gere S~ray P61m~

G i s>:~arge

  • l e" be11 rn) ~a66 l be11 Prsss *1rs Geel a Rt IRjeGtieR (bPG I ) Systsm

~

~

~

4-.

~ ReaGter Steam Geme Prsss~re be11 (Psrmissi,,e)

{)...

be1 I Press 11re Geel a Rt IRjeGtieR P11m~

GiSGRarge *1 e1 I be11 rny~ass)

Shutdown Cooling System (SOC) Isolation

a. Reactor Vessel Water Level-Low Reactor Water Cleanup System Isolation
a.

Reactor Vessel Water Level-Low RPV Water Inventory Contro l Instrumentation

3. 3. 5. 2 Table 3. 3. 5. 2-1 (Page 1 of lJ RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4-,----4

~

( {} )

~

( {} )

REQUIRED CHANNELS PER FUNCTION

~

~

1 1m~ (al

~

lee~ ( 3) per trip system per trip system bGNl:llTIGMS R>*rnrnGrn

~

R>Q" IRrn SllR" U bb ' MG>

' bTIG~I 0. 1 R>Ql lIR>MDIH

~ L~

. 9

. 2

. 2

~ :i. :i. 8. 2. 2

~ ;J.:J.9.2.2

~ ;i. ;i. 9. 2. 2

~ ;i. ;i. 9. 2. i

~ ;i. ;i. 9. 2. 2

~ ;i. ;i. 9. 2. 1

~ ;i. ;i. 9. 2. 2 ALLOWABLE VALUE

,,; ;J41.7 ~sig

,,; ;J41.7 ~sig llG? g~m

~ 2. 65 inches

~ 2. 65 inches 0 sseGiate9 " itR aR.:u:s s~9system re~~ireEJ te 9e GP>R ' H> 9y u:G :l. 9. 2, " RP " 'later IR"eRtery (;eRtrel."

When automatic i solation of the associated penet ration flow path(sJ is credited in calculat i ng DRAIN TIME.

Dresden 2 and 3 3.3. 5. 2-3 Amendment No. 256 / 249

3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LOP Instrumentation 3.3.8.1 LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY:

ACTIONS MODES 1, 2, and 3, ~

'1Jf1 e A Hie assoc i ate El Eli es el

§ e A et at o I" i s I" e q 1:.d I" e El to 13 e OPERABLE B)' LCO 3.8. 2, " AC Sotll"ces SFiutElo'vJA."

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channel in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.

trip.

B.

Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)

Time not met.

inoperable.

Dresden 2 and 3 3.3.8.1-1 Amendment No. 185/180

ACTIONS CON DIT ION

c.

(cont inued)

C. 2 D.

MS IV lea kage ra t e D. 1 not wit hin l imit.

E.

Requ i red Acti on and E. 1 assoc i ated Comp l et i on Ti me of Cond iti on A, AND B' C, or D not met..:i-A-MQg~ +/-' 2 ' 8F d.

E. 2 Dresden 2 and 3 REQUIR ED ACTIO N

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

1.

I so l ation devices in hi gh rad i ation areas may be veri f ied by use of admi ni strative means.

2.

I so l ation devices t hat a re a l ocked, sea l ed, or otherwise secured may be verified by use of admi nistrative means.

Ver i fy the affected penetrat i on fl ow path is i so l ated.

Restore leakage ra t e to wit hin l i mit.

Be i n MOD E 3.

Be i n MODE 4.

PC I Vs 3. 6.1. 3 COM PLETI ON TI ME Once per 31 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 /> 3. 6.1.3-5 Amendment No. 256 / 249

ACTIONS CONDITION B.

One required DG inoperable.

B.1 B.2 B.3 REQUIRED ACTION Suspend CORE ALTERATIONS.

Suspend movement of recently irradiated fuel assemblies in secondary containment.

Initiate action to restore required DG to OPERABLE status.

AC Sources-Shutdown 3.8.2 COMPLETION TIME Immediatel y Immediatel y Immediately SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.

SURVEILLANCE REQUIREMENTS SR 3.8.2.1

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

The following SRs are applicable for The followi g SRs are not required to performed: r~~r.--...+-.--T.---2M+--'7-.e-.--:r--.--:+/-:-1::1----t-tt-H::H:ttl-ft

~R 2. g. 1. 12, ane

~R 2. g. 1. 14 thro~gh

~R 2. g. i. rn.

i------+ ~

AC sources required to be OPERABLE

~Rs of ~pecification 2. g. 1, except

~R 2. g. 1. 9,

~R 2. g. 1. 12,

~R 2. g. 1. 19,

~R 2. g. 1. 20, ane

~R 2. g. 1. 21 are applica8 l e.

SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.15 SR 3.8.1.17 FREQUENCY In accordance with applicable SRs Dresden 2 and 3 3.8.2-3 Amendment No. 26g/26 1

-+

t

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.5.2-4 3.3.6.1-4 3.3.8.1-1 3.5.1-1 3.5.1-2 3.5.2-2 3.5.2-3 3.5.2-5 3.8.2-4

1.1 Definitions DOSE EQUIVALENT I-131 (continued)

DRAIN TIME closed and administratively controlled LaSalle 1 and 2 Definitions

1. 1 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

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 l imiting drain rate;

b.

The limi ting 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 dra i n rates through multiple penetration flow paths susceptible to a common mode failu re (e. g., seismic event, loss of normal

~0 1.1er

, single

~u1man error), for all penet rat ion flow paths below the TAF except:

1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are l ocked, sea l ed, or 0H1ernise seCblred 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 (continued) 1.1-4 Amendment No. 242/228

3.3 INSTRUMENTATION RPV Water Inventory Control Instrumentation -+-

3. 3. 5. 2 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:

ACTIONS According to Table 3.3.5.2-1.

A.1 Initiate action to place channel in trip.

OR

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

Separate Condition entry is a lowed for each channel.

CONDITION

-A-o-0Ae or more cAaAAels iAoperable.

A. One or more

-channels

-r+----i IV inoperable.

As reEJt:li reEl by ReEjuireEl ActioA A.1 aAEl refereAceEl iA Taele 3.3. 5. 2 1.

REQUIRED ACTION EAter tAe CoAElitioA referCAced i A Taele 3.3. 5. 2 1 for tAe cAaAAel.

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

( ~A N~ Initiate action to IQ-/,. r calculate IA.2.2:t---.~ B-: Calculate DRAIN TIME.

C. As reEJui red by ReEjui r eEl ActioA A. 1 aAEl refereAceEl iA Table 3.3.S. 2 1.

Place cAaAAel iA trip.

COMPLETION TIME I

Imme Eli a tel :Y

\\!Immediately I

'+'

Immediately Immediately 1 ROUP (continued)

LaSalle 1 and 2 3.3.5.2-1 Amendment No. 230/216

RPV Water In ventory Control In strumentation ~

3.3.5.2 ACTION S (continued)

CONDITION REQUIRED ACTIO N COMPLETION TIME B.,ais FeEf td Fee B:Y B-:-+

Res=!:sFe eFiaAAel =!:s 24 AS~FS ReEf~i Fee,o,e=t:i SA A. 1 OPERABLE s=!:a=!:~s a A El Fefe FeAeeEl i A

=Fasl e 3. 3. 5. 2 1.

E.

ReEJ~i Fee P.c=!:i SA a AS f-:-1.

Beel a Fe asssci a=!:ee Ifflffleei a=!:el y asssei a=!:ee EGGS i Aj ee=!:i SA 1ls13 Fa:y Gsfflp le=!: i SA =Fiffle sf s~ssys=!:effl iAspeFasle.

GsAElHi SA G SF B AS=!:

m-e+-:-

These SRs apply to each Function in SURVEILLANCE REQUIREMENTS

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

RefeF =!:s Table 3.3.5.2-1 =!:s Ele=!:eFffliAe WAiCA SRs apply fsF eacFI EGGS F~Ac=!:isA SURVEI LLANC E SR 3.3.5.2. 1 Perform CHANN EL CHECK.

SR 3.3.5.2.2 Perform CHANNE L FUNCTIONAL TEST.

LaSal l e 1 and 2 3.3.5.2-2 FREQUENCY In accordance wi th the Survei 11 ance Frequency Control Program In accordance with the Surveil l ance Frequency Control Program Amendment No. 230/216

RPV Water Inventory Control Instrumentation +-

3. 3. 5. 2 Table 3.3.5. 2-1 (page 1 of 2)

+

RPV Water Inve ntory Control Instrume ntatio n

==

FUNCTION h

Le.. PFessriFe Gee l aAt IAjeetieA A (LPG!)

aA8 Le.. PFessriFe GeFe S19Fa)

( LPGSJ Sri13s; stems

..r.-

ReaeteF Steam Beme PFessriFe Le..

(!Ajeeti BA PeFmissi oe)

APP LI CABLE MOD ES OR OTHER SPECIFIED CO NDIT IONS LPGS Prim19

~

Bi sei'1aF§Je Fle.. Le.. (B;13ass)

LPGI Prim13 A

~

Bi sei'1aF§Je Fl s.. Ls.. (B) 13a ss l 4-:-

LPGS aA8 LPGI,',

~

lAjeetieA LiAe PFessriFe Ls..

(lAjeetieA PeFmissioe)

~ LPGI B aA8 LPGI G Sri8s) stems

..r.-

ReaeteF Steam Bsme PFessriFe Ls..

(lAjeetieA PeFmissi.el LPG! Prim13 B aA8 LPGI Prim13 G Bisei'1aF§Je Fle.. Le.. (B)13ass)

LPG! B aA8 LPG! G lAjeetisA LiAe PFessriFe Le..

(lAjeetieA PeFmissi.el REQU IR ED CHANNE LS PER FUNCTION

~

~..+

~

~..+

~

~..+

G8Pl8 IT I8N S REFERDIGEB

-F-R8!4 RE81:1 I RE8 AGTI8PI A. l Sl:IRVEI LLMIGE RE81:1 I REMUITS AL LOWABLE VALUE

.£tf 3. 3. 5. 2. 2 ~

~

.£tf 3. 3. 5. 2. 2 ~

§I'm a AS

< 1835 §J l3m

.£tf 3. 3. 5. 2. 2

~

§Jl3m a AS

< 2111 §I'm

.£tf 3. 3. 5. 2. 2 ~~

.£tf 3. 3. 5. 2. 2

~

~

.£tf 3. 3. 5. 2. 2

~

§Jl3m aAS

< 2111 §I'm

.£tf 3. 3. 5. 2. 2

~

~

(contin ued)

+a-+ Asseeiates.. itR aA EGGS sril3s;stem FeEfriiFe8 te 13e 8PERABLE 13; LG8 3. 5. 2, " RPV ',/ateF !AoeAtef)

GeAtFel. "

LaSal l e 1 and 2 3. 3.5.2-3 Amendmen t No. 230/216

[]

FUNCTION :-

Iii §A PFesstJFe Cs Fe S13Fa)

( llPCSl S)steFA 13-7 ll PGS PtlFA/3 Bi seAaF§e PFeSStJFe Iii §A rnnass) llPCS S) steFA Fl e" Rate Le.. (8)13ass)

~

4-:-

RHR Shutdown Cooli ng System Isolation a. Reactor Vessel Water Leve l -Low, Level 3

~,,.,. Reoctoc Wotec Cleooop (RWCUJ System Isolation a. Reactor Vessel Water Leve l - Low Low, Level 2 RPV Water In ventory Control In strumentation ~

3.3.5.2 Table 3.3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

( !> )

~

( !> )

REQUIRED CHANNELS PER FUNCTION 2 in one trip system 2 in one trip system co~rn IT ID~Js REFERDJCEB

-F-OOM REGl:IIREB ACTION A. 1 Sl:IRVEI LLMICE RE81:1IREMEMTS

~ 3. 3. 5. 2. 2

~ 3. 3. 5. 2. 2

~ 3. 3. 5. 2. 1

~ 3. 3. 5. 2. 2

~ 3. 3. 5. 2. 2 ALLOWAB LE VALUE

> 113. 2 13si§

~~

-a-A4 219~ §/3FA

11. 0 inches
- 58. 0 inches

+a-+

AssseiateEI.. itfl aA EGGS StlBS)SteFA FetjtJiFeE1 ts 13e OPE 11ABLE B) LCO 3. 5. 2, " IWV '.later lAoeAtSF)

CsAtFe l."

~)

When automatic isolation of the associated penetration f l ow path(s) i s credited in calculatin g DRAIN TIME.

LaSal le 1 and 2 3.3.5.2-4 Amendmen t No. 230 / 216

ACT IONS CON DIT ION J.

As requ i red by Re qui red Act i on C.l and referenced i n Ta bl e 3.3.6.1-1.

SURVEI LLANCE REQU I RE ME NTS J.l Primary Containment Isol ation In strumentation 3. 3.6.1 REQUIRED ACT ION Init i ate action to restore cha nne l to OP ERAB LE st at us.

IAit i ate aetieA ts i se l ate Hie Resi E1 1:1a l li e at Remeva l (R llR ) Sl91:1 tE1e.. A Cee li A§ (S BC) S)ste m.

COMPL ET IO N TI ME Immed i at ely IF!HtteEl i a te l )

- - - - --- -- - -- --- -- -- - -- - -- -- - - -- -- -- - -- - -- -- - NOT ES -- -- -- - --- -- - -- --- -- -- - -- - -- --- -- --- --- - - -

1.

Refer to Tab l e 3.3.6.1-1 to determi ne whi ch SRs ap pl y for eac h Primary Contai nme nt Isolat i on Function.

2.

Whe n a chan nel is pl aced in an i noperable sta t us so l ely for pe rfor mance of requi red Survei l lances, entry into assoc i ated Conditi ons and Requi re d Acti ons may be de l ayed f or up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provi ded t he assoc i at ed Funct i on mainta i ns isolation capa bi l i ty.

SURVEI LLANCE SR 3.3.6.1. 1 Perform CHANNEL CHE CK.

SR 3.3.6.1.2 Perform CHANNEL FUN CTIONAL TEST.

LaSalle 1 and 2 3. 3.6.1-4 FR EQ UEN CY In accorda nce wit h t he Sur veil l ance Frequency Co ntrol Program In accordance wit h the Survei l lance Freque ncy Con t ro l Program (cont i nued)

Amendment No. 200/ 187

+

3.3 INSTRUMENTATION LOP Instrumentation 3.3.8.1 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY:

ACTIONS MODES 1,

'1Jf1eA Hie OP CRABLE 2, and 3..., ~

associatee eiese l §eAerator (DC) is re~uiree to be by LCO 3.8. 2, "AG Sources Sl'l uteo*,m."

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channe l in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.

trip.

B.

Required Action and B.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

LaSalle 1 and 2 3.3.8.1-1 Amendment No. H 7/133

ECCS-Operating

3. 5. 1 3.5 EMERGENCY CORE COOLING SYSTEMS CECCS), REACTOR PRESSURE VESSEL CRPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING CRCIC)

SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.

APPLICABILITY:

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

ACTIONS High Pressure Core Spray (HPCS)

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

LCO 3.0.4.b is not applicable to H-P-G-&.

CONDITION A.

One low pressure ECCS injection/spray subsystem inoperable.

LaSalle 1 and 2 A. 1 REQUIRED ACTION COMPLETION TIME Restore low pressure 7 days ECCS injection/spray subsystem to OPERABLE status.

(continued) 3.5.1-1 Amendment No. 230/ 216

ACTIONS CONDITION B.

lligfi PresstH' e Core S~ray (HPCS+ System inoperable.

B.1 B.2 C.

Two low pressure ECCS C.1 injection/spray subsystems inoperable.

D.

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

D.1 E.

One required ADS valve E.1 inoperable.

F.

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

LaSalle 1 and 2 F.1 REQUIRED ACTION ECCS-Operating

3. 5. 1 COMPLETION TIME Verify by Immediately administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE.

Restore HPCS System to OPERABLE status.

14 days Restore one low 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pressure ECCS injection/spray subsystem to OPERABLE status.

Be in MODE 3.

Restore required ADS valve to OPERABLE status.

Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 14 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued) 3.5.1-2 Amendment No. 196/183

RPV Water Inventory Control.+----

3. 5. 2 ACTIONS (continued)

I

.-----------.---------~

CONDITION 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 />.

LaSalle 1 and 2 C.1 C.2 C.3 REQUIRED ACTION Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.

COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Verify each secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

/

-i(SGT)I Verify one sta y

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

(continued) 3.5.2-2 Amendment No. 230/ 216

ACTION S (continued)

COND ITION 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 AND D.2 AND D. 3 RPV Water In ventory Control..+--

3.5.2 REQUIRED AC TION COMP LETION TIME

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

Required ECCS injection/spray subsystem or additional method of water injection sh a 11 be capable of operating without off site electrical power.

Initiate action to Immediately establish an additional method of water inj ect i on wit h water sources capab l e of maintaining RPV water l eve l > TAF for

'.'. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Initi ate action to Immediately establish secondary conta inment boundary.

Initiate action to Immediately isolate each

}-----____

secondary containment penetration flow path

!automatically or LaSal le 1 and 2 r---__, or verify it can be I

~ manually isolated D.4 from the control room.

Initi ate a~

verify one staA~~Y

§as treatmCAt subsystem is capable of being placed in operat i on.

Immediately (cont in ued) 3.5.2 -3 Amendment No. 230/216

NOTES

1. Operation may be through the test return line.
2. Credit may be taken for normal system RPV Water In ventory Control operation to satisfy this SR.

3.5.2 SURV EILLANC E 0EQUIREMENTS (cont inued)

SURVE ILLANC E FREQUEN CY

-&ff 3. 5. 2. 5

'"ITC

~

-I---

p~ 8t PeEjtd PeEI t8 ee lflet f e P S:'J'Stelfl

~'eAt f 1 8111' i:iaHis ei:ieAeEI l::!ASeP aEllfli Ai s=l:Pa=t i 'i'e eeA=l:Pe i.

\\I e Pi f:,', feP He PeEj l::! i PeEI EGGS

+/-A aeeePdaAee i Aj ee=t i 8A1'SFJPa:'7' Sl::!B5:'7'5 t elfl, eae A lfla A l::!a 1,

11~i t A H e

+-

i:ie 11~e P ei:iePa=te EI, a AEI a l::!te lfla=tie 1~a 1 1~e i A He Sl::!P~' ei 11 aAee f 1 8~1 13aH, Hat i 5 Aet iee l<eEI, sea i eEI, 8P

~PeEfl::!eAE :'7' eHe P~vi se seel::!PeEI i A 13es i tieA, i 5 i A He Ge At Pei PPe§Palfl eeP Peet i:iesitieA.

~

SR 3.5.2. Operate the required ECCS i njection/spray In accordance

~

subsys tem through the reci rcul ati on lin e for with the

~ 10 minutes.

Survei 11 ance Frequ ency Control Program t SR 3. 5.2. Verify each valve credited for automatically In accordance

~

isolating a penetration fl ow path actuates with the to the isolation position on an actual or Survei 11 ance simulated i so l at i on signal.

Frequ ency Control Program SR 3.5.2..g

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

~

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance subsystem can be manually operated.

with the Survei 11 ance Frequency Control Program LaSal le 1 and 2 3.5.2 -5 Amendment No. 230/2 16

ACTIONS CONDITION REQUIRED ACTION AC Sources-Shutdown 3.8.2 COMPLETION TIME D.

Required offsite circuit or DG of LCO Item d. inoperable.

D.1 Declare associated Immediately standby gas treatment subsystem, control room area filtration subsystem, and control room area ventilation air conditioning subsystem inoperable.

SURVEILLANCE REQUIREMENTS SR 3.8.2.1 The following SRs are applicable for SURVEILLANCE

- - - - - - - - - - - - - - - - - - -NOTE-&- - - - - - - - - - - - - - - - - - -

+.:-

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.9 tAFS~§A SR 3.8. 1. 11, SR 3.8. 1. 13 tAFS~§A SR 3.8.1.16, SR 3.8. 1. 18, UftE!.

SR 3.8. 1. 19.

~ SR 3.8. 1. 12 aA8 SR 3. 8. 1. 19 are As t Fe ~~i Fe G te Be ffiet.

f.&r AC sources required to be OPERABLE, SRs ef S13ee if ieatieA 3.8. l, eJ(eqit SR 3.8. 1. 8, SR 3.8. 1. 17, aA8 SR 3.8. 1. 20,

a Fe a1313l i casl e.

SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.9 SR 3.8.1.10 SR 3.8.1.14 SR 3.8.1.16 FREQUENCY

, SR 3.8.1.10, SR 3.8.1.14, and In accordance with applicable SRs LaSalle 1 and 2 3.8.2-4 Amendment No. 230 / 216

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.5.2-2 3.5.2-4 3.5.2-5 3.5.2-6 3.6.1.3-1 3.6.1.3-4 3.8.2-5

Definitions

1. 1 1.1 Definitions (continued)

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 i s 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 eveRt,

l oss of Rormeil poi,ier, siRgle hblmeiR error),

for all penetration flow paths below the TAF except:

closed and administratively controlled

1.

Penetration flow paths connected to an intact closed system, or i so lated by manual or automat ic va l ves that are Quad Cities 1 and 2 l ockeEi, seei l eEi, or otheni'i se secblreEi 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 wi ll close automatically with out offsite power prior to the RPV water le vel being equal to the TAF when actuated by RPV water leve l 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 commun ication with the control room, i s stat ioned at the controls, and is capable of closing the penetration flow path i solat ion device without offsite power.

(continued)

1. 1-4 Amendment No. 279/274

3. 3 I NSTRUMENTATI ON RPV Water Inventory Control Instrumentation 3.3. 5.2 3. 3. 5.2 Reactor Pressure Vesse l (RPV) Water Inventory Contro l Instrumentat i on LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentat i on for each Funct i on in Table 3.3.5.2 -1 shal l be OPERAB LE.

AP PLI CAB ILITY:

According to Tab l e 3.3.5.2-1.

ACTIONS

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

Separate Cond i tion entry is al lowed for each channel.

A.1 Initiate action to place channel in trip CON DIT ION OR COMP LETI ON TI ME

/Jr..

0Ae 8P lfl8Pe cl9aAAel s A-:-

EA:f:et"

=E 19 e CeAE1it:ieA IlfllfleE1i at: el y i Ae13 n a 131 e.

PefereAceE1 i A Tas le 3. 3. 5. 2 1 fep rllmmediately I A. One or more He el9aAAel.

r channels inoperable.

.J JV

'4 B-:-

As PeEjui PeE1 B:Y

£-:-+

Dec l are assoc i ated Immediate l y ReEjui PeE1,01c=EieA A. 1 IA~.11 penetration fl ow a As Pe:fePeAces i A path(s) incapable of Ta sle 3.3. 5. 2 1.

automatic isolation.

c ~

f Initiate action to calculate IA.2.2 H ~ -B-ti-Cal cul a=Ee DRA IN TI ME.

Immed i ate l y

c. As PeEjUi PCS B)'

-:-+

Place CAaAAel i A fPij3.

1 A8UP ReEjUiPeS Ac=EieA A. 1 a A E1 PefePeAeeE1 i A

i:a 81 e 3.3. 5. 2 1.

D. As PeEjUi PeE1 B)'

~ Resf:epe el9aAAel f; 0 2q A8UPS ReEjuiPe8 Act:ieA A. 1 OPERABLE st:a t:us.

a AE1 PefePeAeeE1 i A Tasle 3.3. 5. 2 1.

(continued) I Quad Ci t i es 1 and 2 3.3.5.2-1 Amendment No. 273/268

ACTIONS COND IT ION RPV Water Inventory Control Instrumentation 3.3. 5.2 REQUI RED ACTION COM PLETI ON TIM E

- J E. ReEjtl i FEEi Aet i sA a A El f-:4.

Deel a Fe assseiateEI l S\\i' l A'IA'leEl i a tel y assseiateEI GSA'if3 l et i SA f3FESSl:lFe EGGS

/

f i ffie Sf GsAElitisA G SF i Ajeeti SA11s13 Fa:,*

D A St ffiet.

StlBS:)'Steffi i As13eFa l=Jl e.

rJThese SRs apply to each Function in I SURV EILLANC E REQ UIREMENTS

-)

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

~ ef:eF ts Tab l e 3.3.5.2-1 ts EleteFA'liAe ld ~i e~ SRs a1313 ly f:sF eae~ EGGS FtlAetisA.

SURV EILLANC E FREQU ENCY I

SR 3.3.5. 2. 1 Perform CHANNE L CHECK.

In accordance with the Surve i 11 ance Frequency

-)

Control Program..

SR 3.3.5.2. 2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Survei 11 ance Frequency Control Program Quad Ci t i es 1 and 2 3.3.5.2-2 Amendment No. 273/268

FUNCTION h

Ge Fe S13Fa; S; stelll tt7 Reaete1-Stealll Bellle P1 esst:H'e Le (Pe:lllissi.el tr.

GeFe S13Fa)

P~lllf3 Bi SEAaF§e Fl e Ls (8)13assl b

Le.. P1 ess~1 e Geel a19t IAjeetieA (LPG!) S;stelll

~

tt7 ReaeteF Stealll Bellle PFess~Fe Le..

(PeFl!lissi el tr.

Le Press~Fe GeelaAt IAjeeti SA P~lllf3 Bi SEAaF§e Fl e Le (B;13assl RHR Shutdown Cooling System (SOC) Isolation

a. Reactor Vessel Water Level-Low 4..,.

Reactor Water Cleanup (RWCUJ System Isolation

a.

Reactor Vessel Water Level-Low RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3. 3.5. 2-1 (Page 1 of 1)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQU IRED CHANNELS PER FUNCTION

+--!7tt le e13 (al per trip system per trip system G8~18 I TI 8N S REFERUIGEB fiWM RE88IRE9 S8R"EI LL ' NGE AGT I 8N P. l RE88IREMENTS 5-lt

3. 3. 5. 2. 2 5-lt
3. 3. 5. 2. 2 5-lt
3. 3. 5. 2. 2 5-lt
3. 3. 5. 2. 2 5-lt
3. 3. 5. 2. 1 5-lt
3. 3. 5. 2. 2 5-lt
3. 3. 5. 2. l 5-lt
3. 3. 5. 2. 2 ALLOWABLE VALUE

~ 3.8 inches

~ 3.8 inches

' sseeiateEI itA aA EGGS s~BS)Stelll Fe~~i FEEi te se 8PER ' BLE B) LG8 3. 5. 2, " RP" llateF IA eAtSF) GeAtFel. " i calculating DRAIN TIME.

When automatic isolation of the associated penet ration flow path(s) is credited in Quad Cities 1 and 2 3.3.5.2-3 Amendment No. 273/ 268

3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LOP Instrumentation 3.3.8.1 LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY:

ACTIONS MODES 1, 2, and 3, WAeA tAe associated diesel geAerator is reqHired to be OPERABLE by LCO 3.8. 2, " AC SoHrces SAHtdmm."

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channel in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.

trip.

B.

Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)

Time not met.

inoperable.

Quad Cities 1 and 2 3.3.8.1-1 Amendment No. 199/195

ACTIONS CONDITION 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 />.

Quad Cities 1 and 2 C.1 C.2 C.3 RPV Water Inventory Control ~

3.5.2 REQUIRED ACTION Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.

COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Verify each secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

~(SGT) I Verify one sta /

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

(continued) 3.5.2-2 Amendment No. 273 / 268

ACTIONS CONDITION D.

(continued)

D.3 RPV Water Inventory Control t 3.5.2 REQUIRED ACTION COMPLETION TIME Immediately Initiate action to isolate each secondary containment penetration flow path or verify it can be

!automatically or f-------~-' manually isolated D.4 E.

Required Action and E.l associated Completion Time of Condition C or D not met.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE from the control room.

Initiate action to Immediately verify one st aA~~ Y ga s treatmeAt

~.L."::..---r1:SGT I subsystem is capable of being placed in operation.

Initiate action to Immediately restore DRAIN TIME to

~ 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

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 Quad Cities 1 and 2 3.5.2-4 Survei 11 ance Frequency Control Program (continued)

Amendment No. 273/ 268

RPV Water Inventory Control +-

3. 5. 2 SURVEILLANCE REQUIREMENTS SR 3.5.2.2 SR 3.5.2.3 -R 3

. 5

. 2

~

SURVEILLANCE Verify, for the required ECCS injection/

spray subsystem, the:

a.
b.

Suppression pool water level is

~ 8.5 ft; or Contaminated condensate storage tank(s) water volume is~ 140,000 available gallons.

Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

Net l"etji:1i l"e E1 te se FAet fel" sys t eFA 'o'eAt fl 8'oJ

~a t ~ s e ~ e A e E1

~ A E1 el" aE1FAi Ai stPat i ve ceAtl"e l.

VeP ify, fe l" t~ e l"e ~~i l"e E1 EGGS iAj ec tieA /s ~ P a y s ~s sys t e fFI e a c ~

FF1a A ~al

~e 'oJCI" e~el"ate E1 aAE1 a~teFAat i c 'wa l ve iA Hie fl 8\\1' ~atA

, tAat is Aet l ecke E1, sea l eE1, el" et~el"wise sec~PeE1 i A ~ esitieA

, is iA t~e cel"l"ect

~ esitieA FREQUENCY In accordance with the Survei 11 ance Frequency Control Program In accordance

'I' with the Survei 11 ance Frequency Control Program

+

IA accePE1aA ce

  • ,;i tA Hi e S~l"vei ll aAce Fl"e~~eAcy GeAtl"e l Pl"e§l"aFA (continued)

Quad Cities 1 and 2 3.5.2-5 Amendment No. 273/ 268

ISR 3.5.2.4 I

-&R-

3. 5. 2.5 NOTES
1. Operation may be through the test return line.
2. Credit may be taken for normal system I

operation to satisfy this SR.

REQU I/REI I

SURVEI LLANCE

'Y Operate the required ECCS injection/spray subsystem t A P S~§A tA e Pec iP c ~latieA liA e for ~ 10 minutes.

r In ventory Control -r 3.5. 2 FREQUENCY In accordance with the Survei 11 ance Frequency

~-

Control Program SR 3.5.2.~----------------------+-------

ISR 3.5.2.6 I

-&R-

3. 5. 2.6 Verify each valve credited for In accordance
3. 5. 2. 7 automatically isolating a penetration flow with the path actuates to the isolation position on Surveil lan ce an actual or simulated isolation signa l.

Frequency

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

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray subsystem can be manually operated.

Control Program In accordance with the Survei 11 ance Frequency Control Program

==========================================================+-'

Quad Cities 1 and 2 3.5.2-6 Amendment No. 273/ 268

3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves CPCIVs)

PC I Vs 3.6.1.3 LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, W~eR associate~ iRstr~meRtatioR is re~~ire~ to ~e OPERAgLE f)er LCD 2. 2. 8. 1, "Primary CoRtaiRmeRt IsolatioR I RstrnmeRtati OR."

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 appl icable Conditions and Required Actions for systems made inoperable by PCIVs.

4.

Enter appl icable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION A.

NOTE--------

A.1 Only appl icable to penetration flow paths with two or more PC I Vs.

One or more penetration flow paths with one PCI V inoperabl e for reasons other than Condition D.

AND Quad Cities 1 and 2 REQUIRED ACTION Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for main steam l in e 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for main steam line (continued) 3.6.1.3-1 Amendment No. 199/195

ACTI ONS CON DIT ION

c.

(con t inued)

C. 2 D.

MS IV leakage rate D. 1 not with i n li mit.

E.

Required Action and E. 1 associated Comp l et ion Time of Cond iti on A, AND B' C, or D not met-+A-MQQi; +/-, 2, er 3.

E.2 Quad Ci t i es 1 and 2 REQU IRED AC TI ON

- - - - - - - - NOT ES- - - - - - - -

1.

I so l at i on dev i ces in high rad i ation areas may be verif i ed by use of adm i ni st rat i ve means.

2.

I so l at i on devices that are locked, sea l ed, or oth erwi se secured may be verified by use of administrat i ve mea ns.

Verify th e affec t ed penetra t ion fl ow path i s i solated.

Restore leakage ra t e to withi n l i mit.

Be in MODE 3.

Be i n MOD E 4.

PC I Vs 3. 6. 1.3 COM PLETI ON TI ME Once per 31 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 /> 3. 6.1.3-4 Amendment No. 273/ 268

SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.2.1 AC Sources-Shutdown 3.8.2 FREQUENCY The following SRs are applicable for

~

f.ef'- AC sources required to be OPERABLE t-J:T.e.

SRs ef SfJcci fi ca ti eA 3. 8. 1, CJ\\CCfJt In accordance with applicable t

SR 3.8. 1. 9, SR 3.8. 1. 13, SR 3.8. 1. 19,

SR 3.8. 1. 20, aA8 SR 3.8. 1. 21, ape SRs

-t-afJfJl i casl e.

SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 Quad Cities 1 and 2 SR 3.8.1.6 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.15 SR 3.8.1.17 3.8.2-5 Amendment No. 273/268

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.3-122a B 3.3-122b 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 3.3-122j B 3.3-168 B 3.3-169 B 3.3-225 B 3.3-228 B 3.3-229 B 3.5-17 B 3.5-18 B 3.5-19 B 3.5-22 B 3.5-23 B 3.5-24 B 3.8-35 B 3.8-36 B 3.8-39

RPV Water Inventory Control Instrumentation B 3. 3. 5. 2 B 3.3 INSTRUMENTATION B 3.3. 5. 2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation BASES BACKGROUND CLINTON The RPV contains penetrations below the top of the active fuel (TAF) that have the potential to drain the reactor coolant inventory to below the TAF. If the water level should drop below the TAF, the ability to remove decay heat is reduced, which could lead to elevated cladding temperatures and clad perforation.

Safety Limit 2. 1. l. 3 requires the RPV water level to be above the top of t he active irradiated fuel at all times to prevent such elevated cladding temperatures.

Technical Specifications are required by 10 CFR 50. 36 to include limiting safety system settings (LSSS) for variables that have significant safety functions.

LSSS are defined by the regulation as "Where a LSSS is specified for a variable on which a safety limit has been placed, the setting must be chosen so that automatic protective actions will correct the abnormal situation before a Safety Limit (SL) is exceeded."

The Analytical Limit is the limit of the process variabl e at which a safety action is initiated to ensure that a SL is not exceeded.

Any automatic protection action that occurs on reaching the Analytical Limit therefore ensures that the SL is not exceeded.

However, in practice, the actual settings for automatic protection channels must be chosen to be more conservative than the Analytical Limit to account for instrument loop uncertainties related to the sett ing at which the automatic protective action would actually occur.

The actual settings for the automatic isolation channels are the same as those established for the same functions in MODES 1, 2, and 3 in +/-rG.Q.

J
J 5 1,

"I!:merr;;rerH:;y GG..re. C.:wliHr;;T

£ystem (I!:CC£ )

I HstnameHtatiGH 1 "

G-.:i:: LCO 3. 3. 6.1, "Primary Containment Isolation instrumentation. "

With the unit in MODE 4 or 5, RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses.

RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2. 1. 1. 3 and the fuel cladding barrier to prevent the release of radioactive material should a draining event occur.

Under the definition of DRAIN TIME, some penetration flow paths may be excluded from the DRAIN TIME calculation if they will be 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.

(continued)

B 3.3-122a Revi sion No. ~

BASES BACKGROUND (continued)

APPLICABLE SAFETY ANALYSES, LCO,

and APPLICAB I LI TY considered considered CLINTON RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2 The purpose of the RPV Water Inventory Control Instrumentation i s to suppor t the requirements of LCO 3. 5. 2,

" RPV Water Inventory Control, " and the definition of DRAI N TIME.

There are functions that ~

r e qt1ire 9.f.G-T m:urnal iHitiatioH G--T-operatioH G..t:.t.f+e EGG.£. iHj e.::tioH/e:pray gyJdgye:ts m r s qt1ire 9.t4 ~ OP.KRAJ;JJ;.,l!;'. b:f J..G.Q. ~

.a.HQ ~

fnH>::tioHe ~

support automatic isol ation of Residua l Heat Removal subsys t em and React or Water Cleanup system penetration flow path (s ) on low RPV water level.

-+/-Re-RW Wa-t-9-r-IHue Htory CoHtrol IHe:trt11+1e HtatioH eYJd)dOrte:

ops ratioH G..t: J,.o.w. pre e:e:yrg ~

~

(J;.,PC£ ), J,.o.w. prs e:e:t1re

.::oolaHt iHj e.::tioH (J;.,PCI ),.a.HQ ~

pre e:e:t1re ~

~

(FIPC£ )

~

gqnip1+19Ht iH uolugg.w.i.tf+/- ~

G..t: ~

gygtgmg.;i,..g.

ggggrilds9.i.H-.t.f+e ~

.f.G-T J..G.Q.

~ 5 ~

With the unit in MODE 4 or 5, RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses. RPV water inventor y cont rol is required in MODES 4 and 5 to protect Safet y Limit 2. 1. l. 3 and the fuel c l adding barri er to prevent t he release of radioactive material shoul d a draining event occur.

A double - e nded gui l lotine break of the Reactor Coolant System (RCS ) is not in MODES 4 and 5 due t o the rn reduced RCS pressure, reduced p ipin stresses, and ducti l e piping systems. I nstead, an event is poe:tt1late 9 i n which a siHgle operator ~

G--T-initiating event a l lows draining of the RPV water inventory through a singl e penetration flow path with the highest f l ow rate, or the s um of the drain rates through mu l tiple penetration f l ow paths suscept ible to a common mode fa i lure (e g, seismic e " eHt, +/-G-&& G..t: Horma l pm 1er, siHgle R-Yrn error ). It is assumed, based on engineering judgment, that while in MODES 4 and 5, one ECCS injection/spray subsystem can be manua l ly initi ated to maintain adequate reactor vessel water l evel.

As discuss e d in Re f e rences 1, 2, 3, 4, and 5, ope rating experience has shown RPV water inventory to be significant to public health and safety. Therefore, RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50. 36 (c ) (2 ) (ii ).

Permissive and interlock setpoints are general l y considered as nominal values without regard to measurement accuracy.

The specific App l icable Safety Ana l yses, LCO, and Applicability discussions are listed below on a Function by Function basis.

(continued)

B 3.3-122b Revi s i on No. ~

0 t-<

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BASES APPLICABLE SAFETY ANALYSES, LCO,

and APPLICAB I LI TY (continued)

CLINTON RPV Water Inventory Contro l I nstrumentat i on

,f--

B 3. 3. 5. 2

~

~

Discharge HG-W = bGW Allo11able Ealtws a-re-R-i-gl+/-

e nough -t-o-e nsure -t-Ba-t- -t-Be-p-ump -t-1--Gw -ra-t-B -i-& sufficie nt.t-o-prote ct -t-Be-p-ump-,- ye-t, G-W e nough -t-o-e nsure -t-Ba-t- -t-Be-closure G-.t: -t-Be-minim um -t-1--Gw ~

-i-& in it i at e g -t-o-

.a,.1.J,..o.w..f.u.l..l. -t-1--Gw

.i.n.-t-o- -t-Be- ~

~

channel G-.t:.t.J:+/-. ~

Discharge ~

= bGW Fnnction -i-&

regnireGl -t-o-oo OPE1UB1E.if+ ll4GDE.£. 4.a-00 ~ ~

-t-Be-associateGI

~

G-r ~

p-ump -i-& reguired -t-o-oo OPEP:AB1E b-y l,CQ. ~

.t-o-e nsure -t-Be- -p-uHlp8-a--r-e-capable G-.t: inj e cting.i.n.-t-o- -t-Be-P: e actor Pre ssure Ee ss e l wH-e-H-manually initiate g

.J-,...a....,..

P:eactor ~

Isolation Cooling (P:CIC) £torage ~

~

= bGW bGW -l-e-v-e.if+ -t-Be-RC-+/--C £torage +e-nk indicate s -t-Be-una'railability G-.t: e.++ ag e quate supply G-.t: make up ~

.f.r.Gfl'I

~

normal source Mormally -t-Be-sldction " al" e s b e tueen

~

~

-t-Be-RC-+/--C £ torage +e-nk a--r-e- ~

~

~

.f.G-r ~

injection ~

w.t.a.k.@.n,.f.r.Gfl'I.t.J:+/-. RC-+/--C £torage ~

Flo1 '9er,.i.ct.t.AA ~

~

.if+ ~

RC-+/--C £torage +e-nk ~

~

a-pre s e lecte d l e u e l,.f-i-r-8-t- -t-Be-suppre ssion pG-G suction ¥a-l-¥e-automatically ope ns, ~

-t-Be-n -t-Be-RC-+/--C £torage

~

sldction ¥a-l-¥e-automatically clos e s

-'+/--R--i-.s-e nsure s -t-Ba-t-e.++ ag e guate supply 4.f: make up ~

-i-& a" ailabl e -t-o- -t-Be- ~

p.ldHlp-.-

M pre " e nt losing suction -t-o- -t-Be-p-ump-,- -t-Be-suction

" al" es ~

interlockeg ~ -t-Ba-t-.t.AA gnppression pG-G suction

~

ffi.U-.£.t. ~ ~

before.t.AA RC-+/--C £torage +e-nk snction

~

automatically clo8 e 8 RC-+/--C £torage -'+/-'-a+l-k hB¥e-l- = bGW eignal8 a--r-B initi a ted -f-r-Gm. -t-wB

-l-e-v-e tranBmitter8

~

~

-i-& arranged.,s.u.G-fi,.t.f+.a.t. either tranem.itter.a.AA a88ociated ~

.c-a-n ~

-t-Be-8uppre88ion pG-G 8Uction ~

-t-o- ~

.a.00 -t-Be-RC-+/--C £torage -'+/-'-a+l-k 8uction

~

-t-o-cloee

-'+/-'-AA RC-+/--C £torage +e-nk be-¥e-+/--

=

bGW Function 7\\llo' rabl e.\\la-1-uB

-i-& B-i-g-A enough -t-o-ensure adeguate p-ump suction fIB.a-G wB-i-1-e wa-te-r -i-& be-i-ng -t-a-keH-.f.r.Gfl'I -t-Be-RC-+/--C £tor age -'+/-'-aFl-k-,...

~

channel8 G-.t: -t-Be-RG+/-G £torage -'+/-'-a+l-k hB¥e-l- = bGW Function a--r-B ~

requireGI -t-o- ~ OPEP:l\\BlE wH-e-H-JWG£. -i-& required -t-o- ~

0.PEP:l\\BlE -t-o-fulfill ffie requirementB 4.f: l,CO ~ 3 2, ~

-i-&

aligne g -t-o- -t-Be-RC-+/--C £torage ~

~

-t-Be-RC-+/--C £torage +e-nk wa-te-r -l-e-v-e -i-& f+O.t. Hithin -t-Be-limit8 G-.t:.£R

~ 3 2

~

(continued )

B 3.3-122d Revi s i on No. ~

BASES APPLICABLE SAFETY ANALYSES, LCO,

RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2

~

.J-.-.G-..-

.fW.C£- ~

Diacharge l?re aatire

  1. .i-gR-(Bypaaa ) a-00

.fW.C£- £ygtem HB-W Ra--t-e = -hGW (Bypagg )

and APPLICAB I LI TY ~

miI:1imt1m.f..l.g..w. i1:rntrt1m.e Hta &re-prg" ige g w prgte ct.t.AA (continued)

.fW.C£-

p.blmp.f.r.GHl g" e rhe atiHg :wfi.ef+.t.AA p.blmp -i-& ope ratiHg a.H-G CLINTON

.t.AA agggciate g iHj e ctioH ~

-i-& ~

~

~

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mi H im 1 'm.f..l.g..w. ~

~

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J,..Q.w.f..l.g..w. a.H-G ~

p.blmp gigch:uge pre gg11re ~

ae i::ia e g, a.H-G.t.AA ~

-i-&

atitomatically cloaed ~

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gpe ratiHg )

GHe-

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w ge t e ct.t.AA ~

£ygtem' g

.f..l.g..w..r.a.t.-.-

~

~

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.t.J:J..e.t..t.AA traHam.itter catia e a.t.AA miHim11m ~

~

.t.Q. ~

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~

e Hgtigh (iHdicatiHg.t.AA p.blmp -i-& ope ratiHg )

~

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GR-Ge-.t.AA cloatire ae tpgiHt

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~

~

W-i-+/-.a-1-&G ~

~

.fW.C£- pbl-Hlp gigchaP3e pre aatire ge cre aaiHg ~

-t-R-e-ge tpoiHt )

~

~

£ygte m. HB-W ~

= -hGW a.H-G ~

~

Diach;;irge l?regg11re = #.i-gR-Allgo;;il?le ~

-i-& ~

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.t.J:J..e.t. pbl-Hlp.f..l.g..w. -r-a-t.e -i-& atifficie Ht w prote ct -t-f+/-e. pt!-ffip-,- -'fe-l-J,..Q.w e ngtigh w e natire.t.J:J..e.t..t.AA cloaure G-f.t.AA m.inimum.f..l.g..w.

~

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~

~

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Diacharge l?re ggnre

  1. .i-gR-Zl ll011ct1?le ~

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w ~

~

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ope r;;itiHg GHe-channel G-f e-aBB-Functign -i-& required.t.G-Be-OJ?EgABLE wf+/-BB-

.fW.CS -i-& r e qtiire d w Be-OJ?Eg?l £JLE fl-¥ bGG ~

-i-n ~

4-

.a-00.a.,..

(continued)

B 3.3-122e Revi s i on No. ~

BASES RPV Water Inventory Control I nstrumentat i on B 3. 3. 5. 2 APPLICABLE RHR System Iso l ation SAFETY ANALYSES, LCO,

4--.-e- -

Reactor Vessel Water Level -

Low. Level 3 and APPLICAB I LI TY (continued)

The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water l evel isol ation instrumentation prior to the RPV water level being equal to the TAF.

The Reactor Vessel Water Level -

Low, Level 3 Function is onl y required to be OPERABLE when automat ic isolation of the associated RHR penetration f l ow path is credited in cal culating DRAIN TIME.

CLINTON Reactor Vessel Water Leve l -

Low, Level 3 signals are initiated from four level transmitters (two per trip system) that sense the d i fference between the pressure due to a constant column of water (reference l eg ) and the pressure due to the actua l water level (variable leg ) in the vessel.

While four channels (two channels per trip system) of the Reactor Vessel Water Leve l -

Low, Level 3 Function are available, only two channels (al l 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, Leve l 3 Al l owable Value (LCO 3. 3. 1. 1 ),

since the capabi l ity to cool the fue l may be threatened.

(continued)

B 3.3-122f Revi s i on No

. ~

BASES RPV Water Inventory Control I nstrumentation B 3. 3. 5. 2 APPLICABLE Reactor Water Cleanup (RWCU) System I solation SAFETY ANALYSES, LCO,

~

- Reactor Vessel Water level -

Low Low, Level 2 and APPLICAB I LI TY (continued)

The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level be i ng equal t o 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 f l ow paths associated with the RWCU System.

ACT I ONS CLINTON Reactor Vessel Water Leve l -

Low Low, Leve l 2 i s 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 actua l water level (variable l eg ) in the vessel.

While four channels (t wo channels per trip system) of the Reactor Vessel Water Level -

Low, Level 2 Function are avai l able, onl y two channels (al l in the same trip system) are required to be OPERABLE.

The Reactor Vessel Water Level -

Low Low, Leve l 2 Allowab l e Value was chosen to be the same as the ECCS Reactor Vessel Water Level -

Low Low, Level 2 Al lowab l e Va l ue (LCO 3. 3. 5. 1 ), since the capabil i ty to cool the fue l may be threatened.

The Reactor Vessel Water Level -

Low Low, Leve l 2 Function is onl y required t o be OPERABLE when automatic i solat ion of the associated penetration flow path is credited in calcul ating DRAIN TIME.

A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels.

Section 1. 3, Completion Times, speci fies t hat once a Condition has been entered, subsequent divisions,

s ubsystems, compone nts, or variables e xpre sse d i n the Condition discovered to be inoperabl e or not wi thin limits will not result i n separate entry into the Condi tion.

Section 1. 3 also specifies that Requ i red Actions cont inue to apply for each additional failure, with Completi on Times based on initial entry into the Condi tion.

However, t he Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory measures for separate inoperable Condi tion entry for each inoperable RPV Water Inventory Control instrumentation channel.

(continued)

B 3.3-122g Revi s i on No. ~

BASES ACTIONS (continued)

IA.1. A.2.1. and A.2.2 A.2.1 CLINTON RPV Water Inventory Control I nstrumentation B 3. 3. 5. 2 P:si;;p;iirs 8 AstiGH A-.-l-8irs -;=;tg ~

.i.fi.t.G..:tJ:+e. apprgpriats CeH8itieH r s f s r s H-;;e g ffi ~

~

~ 5 2 - 1

~

appli-;;abls Cm:i.8iti91:1 r e f e r e H-;;0 8 ffi.:tJ:+e. ~

.i.& FttH-;=;tiGH 8epe H8 e Ht

~

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~,;J:ieiHHQl.i..e. 8ieQ9" HQ8 iHGp@reiblg, CGH8itiGH A.i.&

eHts:rng.f.G+.t.J:i.a.t; QA&lJ'.l.J'.l.91 ~

i;n*gu iggg.f.G+ tr;;i!'.l.gfgr w.t.00 apprgpriate £ttbseqtt@Ht CGHditiGH

~~

" 2 1, """ ~

RHR System Iso l ation, Reactor Vesse l Water Leve l -

Low Leve l 3, and Reactor Water Cleanup System, Reactor Vessel Water Level -

Low Low, Level 2 functions are applicable when automat ic isolati on of the associated penetrati on f~

low path is credited in calcu lating Drain Time.

If t he A.1 instrumentation i s inoperable, Requi red Action ~ irects immediate action to place t he channe l in trip.

With the inoperable c hannel in the t ripped condition, t he remaining channel will iso l ate the penetration f l ow path on low water If both channels are inoperable and p l aced in tr i p,

flow path wi ll be isolated.

Al ternat ive l y,

1--~'-"+J..U..J;;,f;i"°"-_....(;..i;.-..c;~~..,.........,o--,E'e-6f'\\:H:-lE'e-~ t he associated pen et ration.-----.

f l ow path (s )

be i mmediat ely declared incapable of IA.2.2 I a u tomat ic isolat i on.

Re quired Action ~

directs initiat ing action to ca l culate DRAIN TIME.

The calcul ation cannot credit automatic isolation of the affected

-+-

penetration flow path (s ).

t" bG-W-reagtgr " 98891 pr988ttrs 8igHal8 a..r.e- ~

.a...s-psrmi88ius8

.f.G+.:tfi.e. +/-G.w pr988t1T9 EG.C.£. iHj98ti9H/8pray 8t1B8]'8t9m H\\3.Httal ir:iitiatiGH fttH-;=;tiGH8 U

.t.f:i...i.& psrmi8eiue.i.& iHGperabls,

maJ'.l.ttal iJ'.l.itiatiGJ'.l. &f. m

.i.& prgfl.ibiteg Tl:lergfgrg,.:tJ:+e.

pe rmi88i" O Hltl--&t be-pla-;;gd ffi.:tJ:+e. -t-r-i-p QGHditiGH Pitl:iiH 00-tl-T-r W-i-t-R-.:tJ:+e. permi88i" e ffi.:tJ:+e. -t-r-i-p ggr:iditign, manttal iHitia tiGH may-be-perfgrmed

-P-r-i-G-r-

-t-G-plaGiHg.:tJ:+e.

permi88iue ffi.:tJ:+e. tripped 89HditiGH 1

.:tJ:+e. epsratgr G-a-R.t.a.k-e maHttal 8GHtrgl &f..:tJ:+e. ~

~

.:tJ:+e. iHj98ti9H ~

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.i.fi.t.G..:tJ:+e. R-.J2-',l..,...

~

Cgmple tiGH.T.Htte-G-f. ~

.i.& iHts H8 e 8 -t-G-.a-1--1-G.w.:tJ:+e.

gperatgr ~

-t-G-O" alttate.a.fi..lf 8i8QG" ere8 iHGperabilitie8 ~

-t-G- ~

.:tJ:+e.

-;=; J:i a H He l ffi.t.r.i.p...-

(continued )

B 3.3-122h Revi s i on No. ~

BASES ACTIONS (continued)

CLINTON RPV Water Inventory Control I nstrumentation

.+---

B 3. 3. 5. 2 gequired Actiona -Id-.--+/- aH-G ~

~

intended w enaure Wa-t-appropriate actiona a.re- ~

.i.f. multiple, inoperal2le cH.annela PitH.in -t.H-e-

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~

~

gygtgm ~

oo GleclareGl iAopenele uiUi.iA.1. 00.u+/- G+ -t.H-e- ~

p.ump attction ~

oo aligned w -t-00 attppreaaion -pGG-1-., aince,.i.f.

aligned, -t.H-e-function -i-.s-already performed

-'+/-'-Re-.1. OOtJ.r. CompletioA Um -i-.s-acceptal2le 12ecatt8e.i..:t; minimizeg -t.H-e-

.r.i..g..J.;, G-f- ~

~

nee9e9 Pitfiout.a..i:+ a9eqttate

~

aonrcg w.fi.i.l.g. allouiAg.t.i.m ~

r@atoratioA G+

iligAmeAt G-f- ~

p.ump attctioA w -t.H-e-attppreaaioA ~

U

.a..i:+ ~

G+ ~

Qigcf:i.arge ~

= W.w. 12ypa88 function G-.r.

~

£ygtem Qigcf:i.arge Preaaure = filgl+/- G+ ~

~

=

W.w.

12 yp a 8 8 f n Act i o A -i-.s-i Ao pg r a 12 lg, -t-00.r.- -i-.s-.a.;r.i..a.k -t-fi.a-t- ~

a88ociate9 ~

p.ump ~

o" QrHeat ~

.:t.AA p.ump -i-.s-operating aH-G -t.H-e-aaaociated injection.v-a-l¥e- -i-.s-fi.G.-t- -f-tt-l-1-y-Gpe-fi.--

-+/--H-tJi...i-& condition, -t.H-e-operator -Ga-H- -t-a-k-e manttal control G-f- -t.H-e-p.ump aH-G -t.H-e-injection.v-a-l¥e-w enattre -t.H-e-p.ump ~

fi.G.-t-o" erH.eat

~

.:f-4 OOtJ.r. Compl@tion ~

.w..a.a. cfioggn w ~

.t.i.m ~

-t-00 op>Hator w e " alnate aH-G repair.a.f+¥ 9iaCO" >He9 inoperal2ilitiea p-r-i-o-r w declaring -t.H-e-affected 8t1BByBtem inoperable.

-'+/-'-Re-Completion Um+/--& appropriate g-i-¥BB- -t.H-e-ability w manually &t-a-r-t- -t.H-e- ~

pttmp..s- -a-00 GpB-R -t.H-e-inj ection ualueg.a.& neceBBary w enBure -t.H-e-affer;:;ted p.uHlf' OOe..s-fi.G.-t-ouer!::i.eat W-i-t-R -t.H-e-geqttired Ar;:;tion a-BG aBBOGiated Completion Um G-f-ConditionB G, If., G+ E fi.G.-t-me-t,- -t.H-e-aBBOGiated ~

injer;:;tion/Bpray BttbByBtem ma.:r be inGapable G-f-performing -t.H-e-intended fttnGtion, a-BG ~

be der;:;lared inoperable immediately (continued )

B 3.3-122i Revi sion No. ~

BASES (continued)

SURVEILLANCE REQUIREMENTS CLINTON RPV Water Inventory Control Instrumentation B 3. 3. 5. 2 The following SRs apply to As ~

.H+ -t-00 beginning &t: -t-00 $R.&-r -t-00 SR-&.f.G-+/-' each RPV Water Inventory Control instrument Function -a£-B ~

in -t-fi.B SR-& column &t: Table 3. 3. 5.2 - 1.

SR 3.3.5.2.l Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Signific ant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK guarantees that undetected outright channel failure is limited; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL FUNCTIONAL TEST.

Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertaint ies,

including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

(continued)

B 3.3-122j Revision No. ~

BASES ACTIONS (continued)

CLINTON Primary Containment and Drywell Isolation Instrumentation B 3. 3. 6. 1 K.1 and K. 2 If the channel is not restored to OPERABLE status or placed in trip, or any Required Action of Condition I or J is not met and the associated Completion Time has expired, the plant must be placed in a MODE or other specified condition in which the LCO does not apply.

This is done by placing the p l ant in at l east MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach t he required plant conditions from full power conditions in an order l y manner and without challenging plant systems.

L. 1 and L. 2 If the channel is not restored to OPERABLE status wi t hin the allowed Completion Time, the associated SLC subsystem(s) is declared inoperable or the RWCU System is isolated.

Since this Function is required to ensure that t he SLC System performs its intended function, sufficient remedial measures are provided by declaring the associated SLC subsystem inoperable or isolating the RWCU System.

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 acceptable because it minimizes risk while allowing sufficient time for personnel to isolate the RWCU System.

RWCU isolation is achieved by closing 1G33F001 or 1G33F004, which are the containment isolation valves associated with this isolation function.

M. l r M-.-2-,- M J 1, M J 2, M J J, a-AG~

If the channel is not restored to OPERABLE status or placed in trip within the allowed Completion Time, the associated penetration flow path should be isolated (i. e., closing either 1El2-F008 or 1El2 - F009).

However, if the shutdown cooling function is needed to provide core cooling, these Required Actions allow the penetration flow path to remain uniso l ated provided action is immediately initiated t o restore the channel to OPERABLE status G-F w firouide ffie.a+l ~

Gontrol G-f. flOtential radioaGtiue releases.

~

inGhades enstuin~ seGondary Gontainment.i...s-Ol?Kl~~Al3I.:e;:: ;.a.t. e-a-&t-G-H-e-

£ t::rn sH> y Ga-& Tr e a tm en t +£.G.T+. s yg s y s t em.i...s- 0 pg g 71 13 I.E ;

.a.AG seGoAGla:ry GoAtaii:imeflt isolatioi:i Gafla9ility (i e,.a.t. e-a-&t-G-H-e-isolation ¥a-l¥e-a-AG assoGiated inst:rt1mentation -a--:r-e OJ?Eg7\\J3I,E G-F ~

aGGeflta9le 21slmii:iist:r21tiu e GoAt:rols w 21ssn:re isol21tioi:i Gafla9ility ).i-1:+ ~

seGoAGla:ry Goi:it21ii:imei:it a-AG seGondary Gontainmeflt 9yflass fJenetration ~

~

~

isolated tJ+a.t..i...s-asst1med.t.G.9e isolated.t.G miti~ate (continued )

B 3. 3-168 Revi sion No. +/--G.=4

BASES ACTIONS the channel is restored to OPERABLE status.

CLINTON Pri mary Contai nment and Drywe l l Iso l ation I nstrumentat i on B 3. 3. 6. 1 M. l, M-.--6, M J 1, M J 2, M J J,.a-AG M-.--J-.-4 (conti nued )

radioactiuity r e l e a£ e £ Tu-i ~

Pe-pe rforme d aS-a+/-+

admiI:1i2trati" e cJ::J.e ck, b¥ e xaminiI:1g ~

~ ~

information, w de t e rmiA e.i..f. ~

compone nt£.a.r.e.g.y..j; Q..f ge p rice ~

mainte nance ~ ~

r e a£On£

.J.t..;i,..a. fl4t.

ngcggg:;iry w pgrform.t.J::J..- £HP'9ill:;incgg nggdgd w dgmon2tr:;itg

.t.00 0PE1U'1H1.ITY Q..f.t.00 Gompon0i:i.tg

.r..f.,.. J::J.o\\'G" Gr, d-Wf r e quire d Gompoi:i.e i:i.t.;i,..a. iAope rabl e, -tRe-A -i-t-m-&t-Pe-r e 2tore d w

QpEg 71 ~.bE 2tatu£

.I-fl-.t.fl..i-& Ga-&e-r ~

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Gompone nt w QPEg 11 ~1.E gtatug Ii:i. additioi:i.,.a..t. J,..e..a.,s..t. ' ~

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~

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~

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coi:i.trol Q..f potGi:i.ti:;il radioaGti" G rglg:;iggg W.i.tJl..t.00 appropri:;itg admii:i.iatrati" e Gontrol£ J::\\oPe " er, -tR-e Gloa e d Q.Q..g.r. &a-1:+ ~

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acG eptable 4u-e-w ~

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~

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progre ££ioi:i. Q..f e ue nt£ ~

~

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imme diate rglg:;igg G-f appr9Giablg fi££ion prodnGt£ w

.t.J::J..- Goi:i.t:;iinmgi:i.t

itmoapJ
:J.grg Act i ons must continue unti l;f\\.a..l.l. rgq11irgmgi:i.t£ Q..f

.tR--i Condition.a.r.e £ati2fie d I

N. l, N. 2. 1, and N. 2. 2 If the channel is not restored to OPERABLE status or placed in trip within the allowed Comp letion Time, the associated penetration flow path (s ) shoul d be isol ated (Required Action N. l ).

I solating the affected penetration flow path (s ) accompl ishes the safety function of the inoperable instrumentation.

Alternately, the p l ant must be placed in a condition in which the LCO does not apply.

If applicable,

movement of recent l y irradiated fuel assemblies (i. e., fuel that has occupied part of a critical reactor core wi t hin t he previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ) must be i mmediate l y suspended.

Suspension of these activit i es shal l not preclude completi on of movement of a component to a safe condition.

(continued)

B 3. 3-1 69 Revi s i on No. G.=2-

BASES APPLICABLE SAFETY ANALYSES,

LCO, and APPLICABILITY CLINTON LOP Instrumentation B 3. 3. 8. 1 l. a, l. b, 2. a, 2.b.

4.1 6 kV Emergency Bus Undervoltage (Loss of Voltage) (continued)

The Division 3 4. 16 kV Emergency Bus Loss of Voltage Function 120 - volt Basis trip setpoint is

~ 67 volts and

~ 78 volts.

Six channels of 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) Function per associated emergency bus for Divisions 1 and 2 and four channels for Division 3 are only required to be OPERABLE when the associated DG is required to be OPERABLE to ensure that no single instrument failure can preclude the DG function.

(Six channels input to each of the Division 1 and Division 2 DGs and four channels input to the Division 3 DG.

Each of the six channels for Division 1 and six channels for Division 2 is an inverse time delay relay.

Each of these time delays are considered to be separate channels.

For Divi sion 3, the Loss of Voltage Function logic inputs to a single time delay relay.

Thus,

only one time de l ay channel is associated with Division 3. )

Refer to LCO 3. 8. 1, "AC Sources-Operating, " ~

J.GG J g

~

.!.!.AG £9H:rggg £l:J.Ht.bl9HA 1 " for Applicability Bases for the DGs.

l. c, l. d, l. e, 2.c, 2. d, 2. e.

4. 16 kV Emergency Bus Undervoltage (Degraded Voltage )

A reduced voltage condition on a 4.16 kV emergency bus indicates that while offsite power may not be completely lost to the respective emergency bus, power may be insuffic ient for starting large motors without risking damage to the motors that could disab l e the ECCS function.

Therefore, power supply to the bus is transferred from offsite power to onsite DG power when the voltage on the bus drops below the Degraded Voltage Function Allowable Values (degraded voltage with a time delay ).

This ensures that adequate power will be available to the required equipment.

The Bus Unde rvoltage Al l owable Value s are low e nough to prevent inadvertent power supply transfer, but high enough to ensure that sufficient power is available to the required equipment.

As stated above, the purpose of this instrumentation i s to ensure that sufficient power will be available to support the ECCS function during a LOCA.

During a LOCA, the ECCS and other safety systems will be initiated at the start of the event.

This l arge loading of the safety buses results in a voltage transient of (continued )

B 3. 3-225 Revision No. 4=J.

BASES ACTIONS (continued)

SURVEILLANCE REQUIREMENTS CLINTON B.1 LOP Instrumentati on B 3. 3. 8. 1 If any Required Action and associated Completion Time is not met, the associated Function may not be capabl e of performing the intended function.

Therefore, the associated DG (s ) are declared inoperable immediately.

This requires entry into applicable Conditions and Required Actions of LCO 3. 8. l ~

l.CO] S l, which provide appropriate actions for the inoperabl e DG (s ).

As noted at the beginning of the SRs, the SRs for each LOP Instrumentation Function are l ocated in the SRs column of Table 3. 3. 8.1-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, ent ry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the associated Function maintains DG initiation capability.

Upon completi on of the Surveillance,

or expiration of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> allowance, the channel must be returned to OPERABLE status or the app l icabl e Condition entered and Required Actions taken.

SR 3. 3. 8. 1. 1 This SR has been deleted.

SR 3. 3. 8. 1. 2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. For series Functions, i. e., for the degraded voltage relays in series with their associat ed delay timers, a separate CHANNEL FUNCTIONAL TEST is not required for each Function, provided each Function is tested.

A successfu l test of the required contact (s) of a channel relay may be performed by the verification of the change of state of a singl e contact of the relay.

Th is c l arifies what is an acceptable CHANNEL FUNCT I ONAL TEST of a relay.

This is acceptable because al l of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Surveillance Frequency is control l ed under the Surveillance Frequency Control Program.

(continued)

B 3. 3-228 Revi sion No. -+/-4=6

BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES CLINTON SR

3. 3. 8. 1. 3 LOP Instrumentati on B 3. 3. 8. 1 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3. 3. 8. 1. 4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel.

The system functional testing performed in LCO 3. 8.1 e+l-4 J,,G.Q ~

overlaps this Surveil l ance to provide compl ete testing of the assumed safety functions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

1.

USAR, Section 8. 3. 1.1. 2.

2.

USAR, Section 5. 2. 2.

3.

USAR, Section 6. 3. 3.

4.

USAR, Chapter 15.

5.

I P Calculati on 19-AN-1 9.

B 3. 3-229 Revi sion No. -+/-4=6

RPV Water Inventory Contro l B 3. 5. 2 B 3. 5 EMERGENCY CORE COOLING SYSTEMS (ECCS ), REACTOR PRESSURE VESSEL (RPV )

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

SYS TEM B 3. 5. 2 RPV Water I nventory Control BASES BACKGROUND APPLICABLE SAFETY ANALYSES The RPV con tains penetrations be l ow t h e top o f the active fuel (TAF ) t hat have the potential to drain the react or coo l ant inventory to be l ow the TAF.

If the water leve l should drop be l ow the TAF, the ability to remove decay heat is reduced, wh ich could lead to elevated cladding temperatures and c l ad perforation.

Safety Limit 2. 1. l. 3 requires the RPV water l evel to be above the top of t he active irradiated f uel at all times to prevent such elevat ed cladding temperatures.

With t h e unit in MODE 4 or 5, RPV water inventory contro l is not required to mitigate any events or accidents eva l uated in the safety analyses.

RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2. 1. 1. 3 and the fuel c l adding barrier to prevent the re l ease of radioactive material to the environment should an unexpected draining event occur.

!considered I D gg n b l e ended qui:l,lotine break of the Reactor Coolant System (RCS ) is no~ p98ttt l atgg in MODES 4 and 5 due t o the reduced RCS pressure, reduced piping stresses, and ducti l e

....-~~~~~~~~-

piping systems.

Instead, an event is considered in which an event that creates singlg gpgratgr m G-r-in i tiating event a l lows draining of a drain path through multiple vessel penetrations located below top of active fuel, such as or LCO CLINTON the RPV water inventory through a singl e penetration flow path with the highest f l ow rate, or the sum of the drain rates throu h mu l ti le enetration f l ow a h suscept ible a common mode fa i lure

(~

sgismi8 gugnt, loss of normal power, single human error ).

It is assumed, based on engin ring judgment, that while in MODES 4 and 5, on e l ow pre ssu e ECCS injection/spray subsyste m can maintain adequa e reactor vessel water level.

to As discussed in References 1, 2, 3, 4, and 5, operating experience has shown RPV water inventory to be significant to public health and safety.

Therefore, RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50. 36 (c ) (2 ) (ii ).

The RPV water l eve l must be controlled in MODES 4 and 5 to ensure that if an unexpected draining event should occur,

the reactor coolant water level rema i ns above the top of t he active irradiated f uel as required by Safety Limit 2. 1. 1. 3.

The Limiting Condition for Operation (LCO ) requires t he DRAIN TIME of RPV water inventory to the TAF to be ~ 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

A DRAIN TIME of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> is considered reasonable to (con tinued )

B 3. 5-17 Revis i on No. ~

BASES LCO (continued}

RPV Water Inventory Contro l B 3. 5. 2 identify and initiate action to mitigate unexpected draining of reactor coo l ant.

An event that cou l d cause l oss of RPV water inventory and result in the RPV water level reaching the TAF in greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> does not represent a significant chal l enge to Safety Limi t 2. 1. 1. 3 and can be

.--~~~~~~ managed as part of normal plant operation.

from the control room aligned and OPERABILITY of the ECCS injection/spray subsystem includes any necessary valves, instrumentation, or controls needed to manually align and start the subsystem from the control room.

CLINTON One ECCS injection/spray subsystem is equire OPERABLE and capabl e of being manually started to provide defense - in - depth should an unexpected draining event occur.

n ECCS injection/spray subsystem is defined as either one of the three Low Pressure Coo l ant Injection (LPCI }

subsystems, one Low Pressure Core Spray (LPCS } System, or one High Pressure Core Spray (HPCS } System.

The LPCI s ubsys t em and the LPCS Sys t em cons i st of one motor driven pump, piping, and valves to transfer water from the suppression pool to the reactor pressure vessel (RPV ).

The HPCS System cons i sts of one motor dr i ven pump, piping, and valves to transfer water from the suppression poo l or RC I C storage tank to the RPV.

Management o f gas voids is important to ECCS injection/spray subsystem OPERABI LITY.

The LCO is modif i ed by a Note t hat al l ows a LPCI subsystem to be inoperabl e during a l ignment and operation for decay heat removal with reactor steam dome pressure less than t he residual heat removal cut - i n permissive pressure.

Th is is necessary since the RHR system is requ ired to operate in the shutdown coo l ing mode to remove decay heat and sensible heat from the reactor, and manual realignment from the shutdown cooling mode to t he LPC I mode cou l d r esul t i n pump cavitation and voiding in the suction piping, resulting in the potential to damage the RHR system, inc l uding wat er hammer.

One LPC I s ubsystem is a l lowed to be considered inoperable for this temporar y period, because in s h ut down cooling mode it i s fu l fil l i ng a decay heat remova l capaci t y f unction.

At these low pressures and decay heat levels, a reduced compl e ment of ECCS s ubsystems should provide the required core cooling, thereb y a l lowi ng operation of RHR shutdown coo l ing when necessary.

Becau se of the restrictions on DRAIN TI ME, sufficient time wil l be available fo l lowi ng an unexpected dra i ning event to manua l ly align and operate t he re quired LPCI subsystem to maintain RPV wat er inventory prior t o the RPV water l eve l reach ing the TAF.

(continued}

B 3. 5-18 Revis i on No. ~

BASES (continued)

APPLICABILITY RPV Water Inventory Control B 3. 5. 2 "Instrumentation,"

RPV water inventory control is quired in MODES 4 and 5.

Requirements on water inventory ntro l in other MODES are "ECCS, RPV Water r-~c f'7;o~n~t~a~i=.;n:;-e~d~;;i.;;n-;--;L;C;..0

....s;__~

i

>...n Section 3. 3, Inetr1,1mgntat.ign, and other LCOs in ::>ection._).,,, EC.CS.,.- ~

.a.n.Q ~

~

I nugntgry Inventory Control, Cgntrgl RPV water inventory control is required to protect and RCIC System."

Safety Limit 2. 1. 1. 3 which is applicab l e whenever irradiated fuel is in t h e reactor vessel.

ACTIONS CLINTON A. 1 and B. 1 If the required ECCS injecti on/spray subsystem i s inoperable, it must be res t ored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

In this Condition, t he LCO controls on DRAIN TI ME minimize the possibility that an unexpected dra i ning event could necessitate the use of the ECCS injection/spray subsystem, however the defense - in-depth provided by the ECCS injection/spray subsystem is lost.

The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time for restoring the requ i red ECCS i njection/spray subsys t em to OPERABLE status is based on engineering judgment that considers the LCO controls on DRAIN TIME and the low probabil i ty of a an unexpected draining event that would result in a l oss of RPV water i nventory.

If the inoperable ECCS injection/spray subsystem is not restored to OPERABLE status within the required Completion Time, action must be initiated immedi ately to establish a method of water i njection capab le of operating without offsite electrical power.

The method of water injection includes the necessary ins t r umentation and control s, water sources, and pumps and va l ves needed to add water to the RPV or refueling cavi ty should an unexpected draining event occur.

The method of water injection may be manually operated and may consist of one or more systems or s ubsys t ems, and must be able to access water inventory capabl e of maintaining the RPV water level above the TAF for

~ 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

If recircu l ation of injected water would occur,

i t may be credited in determining the necessary water volume.

(continued)

B 3. 5-19 Revis i on No. ~

BASES ACTIONS Required Actions D.2, D.3, and D.4 are considered to be met when secondary containment, secondary containment penetrations, and the Standby Gas Treatment System are OPERABLE in accordance with LCO 3.6.4.1, LCO 3.6.4.2, and LCO 3.6.4.3.

CLINTON RPV Water Inventory Control B 3. 5. 2 0. 1, 0. 2, 0. 3, and 0. 4 (continued) operated and may consist of one or more additional method of water injection must be able to access water inventory capable of being injected to maintain the RPV water level above the TAF for ~ 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The additional method of water injection and the ECCS injection/spray subsystem may share all or part of the same water sources.

If recirculation of injected water would occur, it may be credited in determining the required water volume.

Should a draining event lower the reactor coolant level to below the TAF, there is potential for damage to the reactor fuel cladding and release of radioactive material.

Additional actions are taken to ensure that radi oactive material will be contained, diluted, and processed prior to being released to the environment.

The secondary containment provides a control volume into which fission products can be contained, diluted, and processed prior to release to the environment.

Required Action D. 2 requires that actions be immediately initiated to establish the secondary containment boundary.

With t he secondary containment boundary established, one SGT subsystem is capable of maintaining a negative pressure in the secondary containment with respect to the environment.

The secondary containment penetratio automatically Or secondary containment boundary.

Req requires that actions be immediately i nitiated to verify that each secondary containment pen ation flow path is isolated or to verify that it can be manually isolated from the control room.

Examples of manual isolation from the control room coul d include the use of manual isolation pushbuttons, control switches, or placing a sufficient number of radiation monitor channels in trip.

A secondary containment penetration flow path can be considered isolated when one barrier in the flow path is in place.

Examples of suitable barriers include, but are not limited to, a closed secondary containment isolation damper (SCIO), a closed manual valve, a blind flange, or another sealing device that sufficiently seals the penetration flow path.

The primary containment upper personnel airlock and other primary containment penetrations that bypass secondary containment are considered part of the secondary containment boundary ;

therefore, they must be considered when completing this action.

One SGT subsystem is capable of maintaining the secondary containment at a negative pressure with respect to the environment and filter gaseous releases.

Required Action 0. 4 requires that actions be immediately initiated to verify that at least one SGT subsystem is capable of being placed in operation.

The required verification is an administrative activity and does not require manipulation or testing of equipment.

(continued )

B 3. 5-22 Revision No. G-=6

BASES ACTIONS (continued}

SURVEILLANCE REQUIREMENTS closed and administratively controlled CLINTON E. 1 RPV Wate r Inventory Control B 3. 5. 2 If the Required Actions and associated Completion times of Conditions C or D are not met or if the DRAIN TIME is less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, actions must be initiated immediately to restore the DRAIN TIME to 2 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

In this condi t ion,

there may be insufficient time to respond to an unexpected draining event to prevent the RPV water inventory from reaching the TAF.

Note that Required Actions D. 1, D. 2, D.3,

and D.4 are also applicable when DRAIN TIME is less t han 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SR

3. 5.2. 1 This Surveillance verifies that the DRAIN TIME of RPV water inventory to the TAF is 2 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The period of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> is considered reasonable to identify and initiate act ion to mitigate draining of reactor coolant.

Loss of RPV water inventory that would result in the RPV wat er level reaching the TAF in greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> does not represent a significant challenge to Safety Limit 2. 1. 1. 3 and can be managed as part of normal plant operation.

The definition of DRAIN TIME states that realistic cross -

sectional areas and drain rates are used in the calculation.

A realistic drain rate may be determined using a single,

s t ep-wise, or integrated calculation considering the changing RPV water level during a draining event.

For a Control Rod RPV penetration flow path with the Control Rod Drive Mechanism removed and not replaced with a blan k flange, the realistic cross - sectional area is based on the control rod blade seated in the control rod guide tube.

If the control rod blade will be raised from the penetration to adjust or verify seating of the blade, the exposed cross -

sectional area of the RPV penetration flow path is used.

The definition of DRAIN TIME excludes from the calculation those penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are lggJrnd, sealed, e.+/-:- gtJ::ierFise semued -i+l-.tfi.e Gl esed i;w sit i eH,

blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths.

A blank flange or other bolted device must be connected with a sufficient number of bolts to prevent draining -i+l-.tfi.e ~

~ e.++

OperatiHg E-a-&i-& Earthg+iake.

Normal or expected leakage from closed systems or past isolation devices is permitted.

Determination that a system is intact and closed or isolated must consider the status of branch lines.a.HG eHgeiHg p-l.a.H.t.

maiHteH3.H8 e.a.HG t es tiHg a Gtiuities.

The Residual Heat Removal (RHR} Shutdown Cooling Syst em is only considered an intact closed system when misalignment (continued}

B 3. 5-23 Revi sion No. ~

BASES SURVEILLANCE REQUIREMENTS SR 3.5. 2. 1 (continued)

RPV Water Inventory Control B 3. 5. 2 issues (Reference 6) have been precluded by functional valve interl ocks or by isola

~

~-~

temporary alterations in The exclusion of penetration fl w ~

from the j.......J::ie.t..e..r:ri:LJ....I:i..a.!~*~9 n of DRAIN TIME consider the pgtgntial support of maintenance effects m

.Q+/- initiating ~

.Q.f:l.

....--.!::::::==========~ -i-t.em.& guppgrting mainte n:rnce a.00 t e gting (rigging,

If reasonable controls are scaffolding, temporary shielding, p i ping plugs, gnubbe r implemented to prevent r

u failu re G-f. such.i-t.em&

,___ ___________ ____, ~

r e ettlt

~

a draining event from a closed temporary alterations from causing the effect of the temporary alterations on DRAIN TIME need not be considered.

Reasonable controls include, but are not limited to controls consistent with the guidance in NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision4, N UMARC 91-06, "Guidelines for Industry Actions to Assess Shutdown Management," or commitments to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants."

CLINTON system or between the RPV and the isolation device,

pgngtratign.f..l.g.w p.a..t.A ~

f:l..9.t. w gxcl 1 g;lgg ~

~

~

calc11latign.

Surveillance Requirement 3. 0. 1 requires SRs to be m between performances.

Therefore, any changes in pl conditions that would change the DRAIN TIME require new DRAIN TIME be determined.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3. 5. 2. 2 and SR 3. 5. 2. 3 The minimum water level of 12 ft 8 inches required or the suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for the ECCS pump, recirculation volume, and vortex prevention.

With the suppression pool water level less than the required limit, the required ECCS injection/spray subsystem is inoperable unless it is aligned to an OPERABLE RCIC storage tank.

With regard to suppression pool water level values obtained pursuant to this SR, as read from plant indicat i on instrumentation, t he specified limit is not considered to be a nominal value with respect to instrument uncertainties.

This requires additional margin to be added to the limit to compensate for instrument uncertainties, for implementation in the associated plant procedures (Ref. 2).

When the suppression pool level is < 12 f t 8 inches, the HPCS System is considered OPERABLE only if it can take suction from the RCIC storage tank and the RCIC storage tank (continued)

B 3. 5-24 Revi sion No. ~

BASES LCO (continued)

AC Sources -

Shutdown B 3. 8. 2 the ability to manually start a e l ectrical power s upport, assuming a loss of the o fsite circuit.

Simi l arly, when the high pressure core s ray (HPCS ) is required to be OPERABLE, a separate offs ' te circuit to the Di vision 3 Class lE onsite electri c l power distribution subsystem, or an OPERABLE Division 3 G, ensure an addi t i ona l sour ce o f powe r f o r the HPCS.

Toget e r,

OPERABI LITY of the required offsite c i rcuit (s ) an DG (s )

ll.5e::..!n.!s~u~res:.:::Su---:;:)'il" 9 Aatt:r 9 the availability o f s ufficient AC sources to operate the p l ant in a safe manner and to mitigate the consequences of pos t ulated events during shutdown (e. g., fue l handling accidents ).

CLINTON The qualified offsite circui t (s ) must be capable of maintaining rated frequency and vo l tage whi l e connect ed to their respective ESF bus (es ), and accepting required loads during an accident.

Qualifi ed offsite circuits are t hose that are described in the USAR and are part of t he licens i ng basis for the plant.

The offsite circuit consists of incoming breaker and disconnect to the respective reserve auxiliary transformer (RAT) or emergency reserve auxiliary t r ans f o r mer (ERAT ), and the respect i ve c ircui t path including feeder breakers t o all 4. 16 kV ESF buses required by LCO 3. 8. 10.

I n addition, an onsite, permanent l y instal led static VAR compensator (SVC ) is availab l e for connect ion to the offsite c i rcuits to s upport required vol t age for t he ESF busses.

Connecti on of the SVC to the offsite circuit i s via circuit breakers to t he secondary side of the RAT and/or ERAT.

Connect ion and operation of the SVC (s ) is dictated by the existing need for voltage support of t he offsite electrical power source (s ) based on prevailing grid conditions.

Thus,

OPERABILITY of the offsite electrical power source (s ) is norma l ly supported by, but i s not necessari l y dependent on,

connection and operation of the SVC (s ).

The resu l tant i mpact on OPERABI LI TY of t he offs i te e l ectrical sour ce (s )

from disconnecting the SVC (s ) from the offsite circuit (s )

can be determined by analysis based on u se of an established model of the o f fsite transmi ssion network and existing grid conditions, including available generating sources, which can be updated on a dai l y or more frequen t bas i s.

The mode l provides the capability to predict or determine what the onsite voltages would be at the RAT and/or ERAT (while connected to the offsite electrical sources ) under maximum postu l ated load conditions.

(continued )

B 3. 8-35 Revi sion No. ~

BASES LCO (continued)

APPLICABILITY CLI NTON AC Sources~Shutdown B 3. 8. 2 being manually started The required DG must be capable of etartiHg, accelerating to rated speed and vo l tage, and connecti ng to its respective ESF bus ~ 9ete,-;ti9H Q..f. ~

tiA90P'91Lige, and accepting required loads.

~

2:Qr;;_{PQAQQ ffit.1-8-t-b. :;i,-;,-;gmpl igl:J.gg Hitl:l.i H

-+/-- 2:8Q9Hda EaGR-JdG ffit.1-8-t-a-l-8-G-be-,-;apablg Q..f. a,-;,-;eptiHg r eqtiire9 ~

u i tl:l.i A -t-RB-aggi;ime9 l oa9 i Hg 2eqtieA>Je iHtOP'ale, 6-A-d ffit.1-8-t- >J9AtiAtie -t-9 gperate tl-H-t-i-l-gff2ite pG-We-r-

~

~ regtgre9 -t-9 -t-RB- ~

bi;ises

~

,-;apabi l itieg.a-r reqi;iire9 -t-9 ~ m.t..f..r.m.eo " ariety Q..f. iAitial Q9A9iti9Ae ~

.a-g.+.

JdG.H:+ ataA9by.w-i-t-l:+/-.t.J:+/-. @AgiAQ ~

6-A-d JdG.H:+ ataH9by

.w-i-t4+.t-l:J..@ @HgiHe a..t; eimbi@Ht Q9A9iti9Aa Additi9Aal JdG

,-;apabilitieg ffit.1-8-t-

&!- dem9Aatrated -t-9 H\\B-t-reqti i red

£tiP'eillaA>Jeg, e--.-g-.-,,-;apability Q..f. -t-RB-JdG -t-9 re" ert -t-9 staAdby 2tati;ig ~

-e>H ECC£- 2igAal wh-i-1-e-gperatiAg.H:+ paral lel

.t-e-s-t. ~

Prgpgr geqneA>JiHg Q..f. l9a9a 1 iA>Jln9iAg trippiAg Q..f.

AQAOaaeHtieil lgagg,

.i..e..eo reqi;iire9 ftiA>Jti9A ~

JdG Qpgg llJH I. ITY I t is acceptabl e for divis i ons to be cross t i ed during shutdown conditions, permitting a s i ngl e offsite power circuit to supply all required AC e l ectrical power distribution subsystems.

No fast transfer capabi l ity is required for off site circuits to be considered OPERABLE for this LCO.

As described in Applicable Safety Analyses, in the event of an accident during shutdown, the TS are designed to maintain the p l ant in a condition s uch that, e¥ef+ :w-i-t-A, ~ siAgle faili;ire, the p l ant will not be in immediate difficulty.

The AC sources required to be OPERABLE in MODES 4 and 5 and during movement of irradiated fuel assemblies i n the primary or secondary containment provide assurance that :

a.

Systems that provide core cooling are ava i lable ;

b.

Systems needed to mitigate a fuel handling accident are availab l e ;

(continued )

B 3. 8-36 Revi sion No. G-=6

BASES ACTIONS SURVEILLANCE REQUIREMENTS SR 3.8.1.7, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.15, SR 3.8.1.18, and SR 3.8.1.19 are not required to be met because DG start and load within a specified time and response on an offsite power or ECCS initiation signal is not required.

lwhich precludes REFERENCES CLINTON C. 1 (continued )

AC Sources ~ Shutdown B 3. 8. 2 additional required AC source is inoperable, and power is s t ill supplied to HPCS, 72 hou rs is a l lowed to restore the additional required AC source to OPERABLE.

This is reasonabl e cons i deri ng HPCS will still pe r fo r m i ts funct i on,

absent an additional singl e failure.

SR 3. 8. 2. 1 SR 3. 8. 2. 1 requires the SRs from LCO 3. 8. 1 that are necessary for ensuring the OPERABILITY of the AC sources in o t her tha~MODES 1, 2, and 3.

SR 3. 8.1. 8 is not requ ired to be met sin e only one offsite circuit is required to be OPERABLE.

In MODES 4 and 5 ECCS injection/spray subsystems are manually controlled in accordance with LCO 3. 5. 2,

"Reactor Pressure Vesse l (RPV) Water I nventory Control."

No ECCS initiation signals are credited for initiation of these subsystems.

Adequate time is availab l e to manually start and load DGs from the Main Control Room in support of RPV inventory control, if required.

Therefore, SR 3. 8. 1. 12 and SR 3. 8. 1. 19, which verify the DG ' s capability to start automatically on actual or simulated ECCS initi ation signal s, are not required to be met i n MODES 4 and 5.

SR 3. 8. 1. 17 is not required to be met because the required OPERABLE DG (s ) is not required to undergo periods of being synchronized to the offsite circuit.

SR 3. 8. 1.20 is excepted because starting i ndependence is not required with the DG (s ) that is not required to be OPERABLE.

Refer to the corresponding Bases for LCO 3. 8. 1 for a discussion of each

<;: P' This SR is modified by a Note~~~

reasgn ~

.t.fte. ~

~

.t.G preclYde requiring the OPERABLE DG (s ) from being paral l eled with the offsite power network or otherwise rendered inoperable during the performance of SRs, and preclude de - energizing a required 4.1 6 kV ESF bus or disconnecting a requ ired offsite circuit during performance of SRs.

With l imited AC sources available, a single event could compromise both the required circuit and the DG.

I t is the intent that these SRs must sti l l be capable of being met, but actua l performance is not required for any DG or offsite circuit.

None.

B 3. 8-39 Revi sion No. ~

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