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MONTHYEARRS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems Project stage: Request ML20122A2302020-05-0101 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of Fleet License Amendment Request to Adopt TSTF-566 Project stage: Acceptance Review RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems Project stage: Supplement ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Project stage: Approval 2020-05-01
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Category:Letter type:RS
MONTHYEARRS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-21-009, Proposed Relief Request Associated with Code Case N-9212022-01-18018 January 2022 Proposed Relief Request Associated with Code Case N-921 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) RS-21-110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-19019 October 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021 Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station RS-21-097, Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning2021-09-15015 September 2021 Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E 2023-08-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21119A1412021-04-29029 April 2021 License Amendment Request, Revise Technical Specifications Administrative Controls Section 5.5.7 Regarding the Frequency for Performing Certain Ventilation Filter Testing RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-021, License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition2021-03-17017 March 2021 License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20337A3012020-12-0202 December 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20323A2542020-11-18018 November 2020 Markup of Proposed Technical Specifications Bases Pages RS-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2020-10-29029 October 2020 License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-20-116, License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative ML20150A0072020-05-29029 May 2020 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process ML20024G4292020-03-0404 March 2020 Record of Decision - Issuance of Subsequent Renewed Facility Operation License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3 RS-20-025, Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2020-02-24024 February 2020 Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) ML19193A0062019-07-12012 July 2019 Supplement No. 7 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19182A1122019-07-0101 July 2019 First 10 CFR 54.21 (B) Annual Amendment to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19158A3122019-06-0707 June 2019 License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources - Operating ML19116A1962019-04-26026 April 2019 License Amendment Request to Revise Technical Specifications 3.8.1, Required Action A.3, for Temporary One-Time Extension of Completion Time ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML19042A1312019-02-11011 February 2019 Supplement No. 3 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. ML19023A0152019-01-23023 January 2019 Supplement No. 2 - Changes to the Subsequent License Renewal Application RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits ML18305B2702018-11-0101 November 2018 Response to Request for Additional Information - License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML18275A0232018-09-28028 September 2018 License Amendment Request to Reduce High Pressure Service Water System Design Pressure and Revise Technical Specifications 3.6.2.3, 3.6.2.4, 3.6.2.5, and 3.7.1 for Temporary Extension of ... ML18271A0092018-09-27027 September 2018 License Amendment Request -Technical Specifications Section 3.3.6.2 Functions 3 and 4 Applicability Changes Pertaining to Reactor Building and Refueling Floor Ventilation ML18257A1432018-09-14014 September 2018 Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18239A3552018-08-27027 August 2018 License Amendment Request - Expanded Actions for LEFM Conditions ML18213A2712018-08-0101 August 2018 Application to Revise Technical Specifications to Adopt TSTF-500, Revision 2, DC Electrical Rewrite Update to TSTF-360, - Supplement 1, Revision of Implementation Dates. ML18193A6972018-07-10010 July 2018 Cover Letter Submitting Subsequent License Renewal Application ML18193A6992018-07-10010 July 2018 Cover Letter Submitting Paper Copies, Cds and Boundary Drawings Accompany Submittal of Subsequent License Renewal Application RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18149A3022018-05-10010 May 2018 Enclosure 4 - Summary of Regulatory Commitments 2023-09-08
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4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-21-016 10 CFR 50.90 January 29, 2021 U.S . Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos.50-277. and 50-278
Subject:
Supplement to Application to Revise Technical Specifications to Adopt TSTF-566 , "Revise Actions for Inoperable RHR Shutdown Cooling Systems"
Reference:
Letter from P.R. Simpson (Exelon) to U.S. NRC, "Application to Revise Technical Specifications to Adopt TSTF-566, 'Revise Actions for Inoperable RHR Shutdown Cooling Systems'," dated April 13, 2020 (ML20104C104)
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), proposed a change to the Technical Specifications (TS),
Appendix A of 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 No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed FOL No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2, Renewed FOL Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed changes are consistent with previously NRC-approved Industry/Technical Specifications Task Force Traveler 566 (TSTF-566), Revision 0, "Revise Actions for Inoperable RHR Shutdown Cooling Systems."
During preparation and review of clean TS pages to be submitted to the NRC, it was identified that the addition of the word "required" for the proposed new Required Action B.1 would result in improved consistency of wording within the TS for Dresden Nuclear Power Station and Peach Bottom Atomic Power Station. The updated marked-up TS pages for these two plants are included in Attachments 1 and 2, respectively. These pages supersede those included in the Reference for these two plants in their entirety.
EGC has reviewed the information supporting a finding of no significant hazards consideration , and the environmental consideration, that were previously provided to the NRC in Reference 1. EGC has concluded
January 29, 2021 U.S . Nuclear Regulatory Commission Page 2 that the information provided in this response does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, EGC has concluded that the information in this supplemental letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), EGC is notifying the State of Illinois and the State of Pennsylvania of this supplement to the proposed TS pages 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 Ms. Rebecca L. Steinman at (630) 657-2831 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 291h day of January 2021 .
Respectfully, Patrick R. Simpson Sr. Manager Licensing Exelon Generation Corporation , LLC Attachments:
- 1. Markup of Proposed Technical Specifications Pages for Dresden Nuclear Power Station
- 2. Markup of Proposed Technical Specifications Pages for Point Beach Atomic Power Station cc: NRC Regional Administrator, Region I NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station Illinois Emergency Management Agency - Division of Nuclear Safety R. R. Janati , Pennsylvania Bureau of Radiation Protection
ATTACHMENT 1 Markup of Proposed Technical Specifications Pages For Dresden Nuclear Power Station Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4. 7-1 3.4. 7-2 3.4.8-1 3.4.8-2
SOC System-Hot Shutdown 3 .4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Shutdown Cooling (SOC) System-Hot Shutdown LCO 3.4.7 Two SOC subsystems shall be OPERABLE, and, with no recirculation pump in operation, at lea st one SOC subsystem sha ll be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required SOC subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required SOC subsystem may be inoperab l e for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.
APPLICABILITY: MODE 3, with reactor vesse l coolant temperature less than the SOC cut -in permissive temperature.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - N0TE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Ir Separate Cond iti on entry is allowed for each SOC subsystem. /'f CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required IAitiate actioA to Iff!ff!edi ately SOC subsystems FestsFe Fe~l:liFed SOC inoperable. s1:Jbsysteffl( s) to OPERABLE stat1:Js .
(continued)
Dresden 2 and 3 3.4.7-1 Amendment No. 212/204
SOC System-Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) Verify an alternate 1 hour method of decay heat removal is available for each inoperable required SOC subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Be iA MODE zq q_ AOl:ff S
!i mmediately I
- - No required SOC Initiate action to Immediately subsystem in restore one required operation. SOC subsystem or one
. recirculation pump to AND operation.
No recirculation in operation.
Verify reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from coolant circulation discovery of no by an alternate reactor coolant B. Required Action method. circulation and associated Completion Time of Condition A not met. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.1 Initiate action to thereafter restore required SOC subsystem(s) to OPERABLE status. Monitor reactor Once per hour coolant temperature and pressure.
Dresden 2 and 3 3.4.7-2 Amendment No. 185 /1 80
SOC System-Cold Shutdown 3 .4.8 3.4 REACTOR COOLANT SYS TEM (RCS) 3.4.8 Shutdown Cooling (SOC) System-Cold Shutdown LCO 3.4.8 Two SOC subsystems shal l be OPERABLE, and, with no recirculation pump in operation, at least one SOC subsystem sha ll be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required SOC subsystems may be not in operation during hydrostatic testing.
- 2. Both required SOC subsystems and recirculation pumps may be not in operat i on for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 3. One required SOC subsys tem may be inoperab l e for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveil lan ces.
APPLICABILITY: MODE 4.
AC TIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each shutdown coo ling subsystem .
CONDITION REQUIRED AC TION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soc subsystems method of decay heat inoperable. removal is available AND for each inoperable required SOC Once per subsystem . 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter 1r--. ~ .
(continued)
I B. Required Action B. 1 Initiate action to and associated restore required SOC IImmediately subsystem(s) to I
Completion Time of Condition A not met. OPERABLE status.
Dresden 2 and 3 3.4.8-1 Amendment No. 185 /1 80
SOC System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME No required SOC Verify reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from d
subsystem in coolant circulating discovery of no operation. by an alternate reactor coolant method. circulation No recirculation pump in operation. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter t
Monitor reactor Once per hour coolant temperature and pressure.
IC.2 I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one SOC subsystem or recirculation In accordance pump is operating. with the Surveillance Frequency Control Program SR 3.4.8.2 Verify SOC subsystem locations susceptible In accordance to gas accumulation are sufficiently filled with the with water. Surveillance Frequency Control Program Dresden 2 and 3 3.4.8-2 Amendment No. 2qq ; 237
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages For Peach Bottom Atomic Power Station Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 REVISED TECHNICAL SPECIFICATIONS PAGES Peach Bottom Atomic Power Station. Unit 2 3.4-16 3.4-17 3.4-19 3.4-20 Peach Bottom Atomic Power Station. Unit 3 3.4-16 3.4-17 3.4-19 3.4-20
RHR Shutdown Cooling System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for perfor mance of Survei 11 ances.
APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each RHR shutdown coo l ing subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A-:-+/- IAitiate actieA te lFAFACSi a tel)'
RHR shutdown cooling l"CStGl"C l"CEjl:Ji l"CS Rll R subsystems inoperable. SAl:JtSG '1/A ceel i A§l Sl:JBS)'StCFA( 5) te OPERABLE stahts .
(continued)
PBAPS UNIT 2 3.4-16 Amendment No. ~
RHR Shutdown Cooling System-Hot Shutdown 3.4.7 ACT IONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> method of decay heat removal is available for each required AND inoperable RHR Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shutdown cooling thereafter subsystem.
Be i A MODE~ . 2~ AOl:ffS
~~ lm
~ m-ed
-i-at-e-ly~~~
£-..;- No RHR shutdown Initiate action to Immediately cooling subsystem in restore one RHR operation. shutdown cooling
~ AND subsystem or one recircu l ation pump to operation.
No in operation.
Verify reacto r 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from B. Required Action coolant circulation discovery of no and associated by an alternate reactor coolant Completion Time of method. circulation Condition A not met.
Once per B.1 Initiate action to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> restore required RHR thereafter shutdown cooling subsystem(s) to OPERABLE status.
Monitor reactor Once per hour coolant tempe r ature and pressure.
PBAPS UNIT 2 3.4-17 Amendment No. ~
RHR Shutdown Cooling System-Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for perfor mance of Survei 11 ances.
APPLICABILITY: MODE 4.
ACT IONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each RHR shutdown coo l ing subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A .1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RHR shutdown cooling method of decay heat subsystems inoperable. removal is available for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t hereafter
( (continued)
B. Required Action B. 1 Initiate action to and associated restore required RHR Completion Time of shutdown cooling IImmediately I Condition A not met. subsystem(s) to OPERABLE status.
PBAPS UNIT 2 3.4-19 Amendment No. ~
RHR Shu tdown Coo li ng System-Cold Shutdown
- 3. 4. 8 AC TIONS (continued)
COND IT ION REQUIR ED AC TI ON COMP LETI ON TIM E
~ No RHR shutdown -&-:-+ Ver i fy reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from
~ coo li ng subsys t em i n coolant ci rcu l ati ng di scovery of no operat i on . by an al ternate reactor coo l ant AND ~ met hod . ci rcu l at i on AN D No rec i rcu l at i on pump i n operat i on. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> therea f ter AND B-; Mon it or reactor Once per hour coo l ant temperature
~
and pressure.
SURVEI LLANC E REQU I REMENTS SURV EILL ANC E FR EQUE NCY SR 3.4 . 8. 1 Ver i fy one required RHR s hutdown cooling In accordance subsys t em or rec i rculat i on pump i s wit h the operating. Surve ill ance Frequency Contro l Program.
SR 3.4.8 . 2 - - - - - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - - - - - -
HP SW system re l ated components are exc l uded.
Ver i fy requ i red RHR shutdown coo li ng In accordance subsys t em l ocat i ons suscept i ble to gas wi t h the accumu l at ion are suffic i ently f il led wi t h Survei 11 ance water. Frequency Contro l Program.
PBA PS UN IT 2 3. 4-20 Amendment No . ~
RHR Shutdown Cooling System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shal l be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required RHR shutdown cooling subsystem may be inopera ble for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Survei 11 ances.
APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A-:4- I Aitiate actieA te l lfllfleE1i ate l ,y RHR shutdown cooling pestel"e l"CEjl:Ji l"CS Rll R subsystems inoperable. s~1:JtE1ewA cee l iA§ Sl:JBS)'Stelfl( 5) te OPERABLE stat1:Js .
(continued)
PBAPS UN IT 3 3.4-16 Amendment No. ~
RHR Shutdown Cooling System-Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACT ION COMPLETION TIME A. (continued) Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> method of decay heat removal is available ~ AND for each required Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable RHR thereafter shutdown coo ling subsystem.
Be iA MODE 4. 24 A Ol:.11"5
~~lm ~m-e-d-ia-t-el-y~~~~
~ No RHR shutdown £--;-} Initiate action to Immediately cooling subsystem in restore one RHR
~ ~
operation. shutdown coo ling subsystem or one AND recirculation pump to operation .
No recirculation ump in operation. AND B. Required Action : Verify reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from and associated coo lant circulation discovery of no
~
Completion Time of by an alternate reactor coo lant Condition A not method. circulation met.
AND 8 .1 Initiate action to Once per restore required RHR 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdown cooling thereafter subsystem(s) to OPERABLE status. AND Monitor reactor Once per hour coolant temperature and pressure.
PBAPS UN IT 3 3.4-17 Amendment No. +4
RHR Shutdown Cooling System-Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required RHR shutdown cooling subsystem may be inopera ble for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Survei 11 ances.
APPLICABILITY: MODE 4.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RHR shutdown cooling method of decay heat subsystems inoperable. removal is ava i lable for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter 11\ I\
(continued)
- 8. 1 Initiate action to
- 8. Required Action restore required RHR IImmediately I and associated shutdown cooling Completion Time of subsystem(s) to Condition A not OPERABLE status.
met.
PBAPS UN IT 3 3.4-19 Amendment No. ~
RHR Shutdown Coo li ng System-Co l d Shutdown 3.4.8 ACT IONS (cont i nued)
COND IT ION REQUIR ED AC TI ON COMP LETI ON TI ME b-&-:- No RHR s hutdown cool i ng subsystem i n operat i on .
-&-:+ Ver ify reactor coo l an t c i rculat i ng by an alt ernate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fro m di scovery of no reactor coo l ant AN D No rec i rcu l at i on pump
~ method . ci rcu l at i on AND i n operat i on. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AN D
~ Mon i tor reac t or Once per hour I~ coo l ant t emperature and pressure.
rc21 SURV EILL ANC E REQ UI REMENTS SURV EI LLANC E FREQU ENCY SR 3 . 4.8.1 Ver i fy one requ i red RHR s hu tdow n coo li ng I n accordance subsystem or rec i rcu l at ion pump i s wit h t he opera ti ng . Surve ill ance Frequency Contro l Program .
SR 3.4.8.2 - - - - - - - - - - - - - - - - - - - NO TE - - - - - - - - - - - - - - - - - - - -
HPSW system re l ated co mponents are exc lu ded .
Ver ify requ i red RHR s hutdown cool i ng In accordance subsystem loca ti ons suscept i bl e to gas wit h t he accu mulatio n are suff i ci ent l y f i l l ed with Surve ill ance water . Frequency Contro l Program.
PBAPS UN IT 3 3. 4- 20 Amendment No . B-B