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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-23-077, 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-23-078, 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-23-042, 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-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-045, 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-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-027, 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-22-023, 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-22-019, 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 RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel 2023-08-30
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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 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 ML20323A2542020-11-18018 November 2020 Markup of Proposed Technical Specifications Bases Pages 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 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 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 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) 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 ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements 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 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 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 RS-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML18053A1832018-01-31031 January 2018 Enclosure 4 - Dresden Units 1, 2 & 3 - Evaluation of Proposed Changes RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1732018-01-31031 January 2018 Attachment 4A - Dresden Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1742018-01-31031 January 2018 Attachment 4B - Dresden Clean Emergency Plan EP-AA-1000 Pages RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-17-174, Additional Supplement to Dresden Nuclear Power Station, Units 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-12-21021 December 2017 Additional Supplement to Dresden Nuclear Power Station, Units 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-17-173, Supplement to Dresden Nuclear Power Station, Units 2 and 3 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-12-20020 December 2017 Supplement to Dresden Nuclear Power Station, Units 2 and 3 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-060, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-0303 May 2017 Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-02-10010 February 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-105, Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2016-04-26026 April 2016 Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings RS-16-016, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-01-20020 January 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel RS-15-237, Dresden Nuclear Power Station, Units 2 and 3/Quad Cities Nuclear Power Station, Units 1 and 2 - Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2015-09-0101 September 2015 Dresden Nuclear Power Station, Units 2 and 3/Quad Cities Nuclear Power Station, Units 1 and 2 - Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-15-237, /Quad Cities Nuclear Power Station, Units 1 and 2 - Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2015-09-0101 September 2015 /Quad Cities Nuclear Power Station, Units 1 and 2 - Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-15-108, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2015-08-18018 August 2015 Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. 2023-05-25
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Text
Exekltn Exelon Generation wwwexeloncorp corn Nuclear 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.90 RS-03-026 January 31, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos 50-237 and 50-249
Subject:
Request for Technical Specifications Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit,"
Exelon Generation Company (EGC), LLC, requests changes to the Technical Specifications (TS) of Facility License Nos. DPR-1 9 and DPR-25 for the Dresden Nuclear Power Station (DNPS),
Units 2 and 3. The proposed changes modify the allowable values (AV) for two Isolation Condenser (IC) System isolation functions, Steam Flow - High and the Return Flow - High, specified in TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation."
These proposed changes support a planned replacement of the existing instrumentation, which is currently environmentally qualified (EQ) to Division of Operating Reactors EQ guidelines, with Class 1 E qualified flow switches. The analytical limits (ALs) for the functions are not changed.
The subject flow switches will be installed during scheduled on-line system maintenance for Units 2 and 3 in the fall of 2003. Therefore, Exelon requests approval of the proposed TS changes by August 27, 2003. Once approved, the amendment is to be implemented within 90 days.
The attachments to this letter provide information supporting these proposed changes and are arranged as follows.
- 1. Attachment A provides a description and safety analysis of the proposed change, our evaluation supporting a finding of no significant hazards, and information regarding an Environmental Assessment.
- 2. Attachment B includes the applicable TS page mark-up with the proposed changes indicated.
- 3. Attachment C contains the revised TS page including the proposed changes.
These proposed TS changes have been reviewed by the DNPS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program.
A Do.
January 31, 2003 U. S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.91 (b), "Notice for public comment; State consultation," EGC is notifying the State of Illinois of this request for changes to the TS by transmitting a copy of this letter and its attachments to the designated State Official.
Should you have any questions concerning his letter, please contact Mr. Thomas G. Roddey at (630) 657-2811.
Respectfully, Patrick R. Simpson Manager - Licensing Mid-West Regional Operating Group Attachments: Affidavit Attachment A: Description and Safety Analysis for Proposed Changes Attachment B: Marked-up Technical Specifications Pages for Proposed Changes Attachment C: Revised Technical Specifications Pages for Proposed Changes cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector- Dresden Nuclear Power Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
STATE OF ILLINOIS )
COUNTY OF DUPAGE
)
IN THE MATTER OF
)
EXELON GENERATION COMPANY, LLC ) Docket Numbers DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3
) 50-237 and 50-249
SUBJECT:
Request for Technical Specifications Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information, and belief.
Patrick R. Simpson Manager - Licensing Mid-West Regional Operating Group Subscribed and sworn to before me, a Notary Public in and for the State above named, this 3 day of
Notary Public 0OFFICIAL ANEULILSE SEAL:
GRISBY 1.TOF ILLINOIS NOTARY PUBLIC, STATE MY COMMISSIONEXIS31320
f Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES
- 1. DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company (EGC), LLC, requests changes to Appendix A, Technical Specifications (TS), of Facility License Nos. DPR-1 9 and DPR-25 for the Dresden Nuclear Power Station (DNPS), Units 2 and 3. Specifically, EGC proposes to revise the allowable values (AVs) for two functions in Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," Function 4, "Isolation Condenser System Isolation." The changes affect Function 4.a, "Steam Flow - High," and Function 4.b, "Return Flow - High." These proposed changes support a planned replacement of the existing high flow isolation instrumentation, which is currently environmentally qualified (EQ) to Division of Operating Reactors (DOR) EQ guidelines, with flow switches qualified to NUREG-0588, "Interim Staff Position on Equipment Qualification of Safety-Related Electrical Equipment," Class 1E and 10 CFR 50.49, "Environmental qualification of electric equipment important to safety for nuclear power plants."
The related plant design changes will be installed during on-line system maintenance scheduled in the fall of 2003. A complete description of the proposed changes is given in Section 2, "Proposed Changes," of this attachment. Attachment B provides the marked-up TS page indicating the proposed changes. Attachment C provides the revised TS page.
EGC has reviewed the proposed changes for impact on any DNPS submittals currently being reviewed by the NRC and has determined that there is no impact on any of these submittals. We request approval of these proposed changes by August 27, 2003, to support switch replacements during the fall of 2003. Once approved, the amendment is to be implemented within 90 days.
- 2. PROPOSED CHANGES For this license amendment request, the two relevant input parameters to the IC isolation logic are IC steam flow and return flow. Currently, two locally-mounted, indicating differential pressure switches are used to monitor each variable. The existing high flow isolation differential pressure switches (i.e., Barton Model No. 288 series) will be replaced with similar Class 1E qualified differential pressure switches (i.e., Barton Model No. 580A-0) that will interface with the existing Primary Containment Isolation System (PCIS) logic. No change is being made to the circuit design or logic. The new differential pressure switches use proven technology, are highly reliable, and are currently used in the Main Steam Line Flow - High function at DNPS Unit 2.
1 DNPS proposes to replace existing switches, qualified to DOR requirements, with switches that are fully qualified to Class 1E requirements. The new switches are qualified to more stringent standards and differ from the existing switches in reference accuracy and in allowed setpoint drift associated with accident conditions. As a result, the calculated AVs for the new differential pressure switches vary from those calculated for the existing switches. The analytical limits are the same for both the existing and proposed replacement switches.
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Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES The proposed changes to the allowable values for Function 4 of TS Table 3.3.6.1-1 are as follows.
- 1. Function 4.a, Steam Flow - High Revise the allowable value from < 290.76% of rated steam flow to < 273.65% of rated steam flow.
- 2. Function 4.b, Return Flow - High Revise the allowable value from _<30.2 inches water (Unit 2) to _ 26.0 inches water (Unit 2).
Revise the allowable value from < 13.7 inches water (Unit 3) to __10.7 inches water (Unit 3).
The proposed TS changes are reflected on a marked-up copy of the affected TS page in Attachment B. The revised TS page is provided in Attachment C.
- 3. BACKGROUND In general, the primary containment isolation instrumentation and logic systems automatically initiate closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, acting in conjunction with other accident-mitigating systems, is to limit fission product release during and following postulated Design Basis Accidents. The isolation instrumentation includes sensors, relays, and switches that are necessary to initiate isolations of the primary containment and reactor coolant pressure boundary. When the setpoint is exceeded, the channel output relay actuates to provide a primary containment isolation signal to the isolation logic.
Monitoring a wide range of independent parameters provides functional diversity.
For this license amendment request, the two relevant input parameters to the IC isolation logic are IC steam flow and return flow. The IC Flow - High functions are provided to detect a break of IC lines, initiating closure of the inboard and outboard steam and condensate return isolation valves and vent line isolation valves. If steam or condensate continues to flow out of the break, the reactor may be depressurized and the core uncovered. Therefore, the isolation is initiated on high flow to prevent or mitigate core damage. Redundant sensor inputs for each parameter provide for isolation initiation. I The IC Steam Flow - High and Return Flow - High functions each receive input from one channel via their respective associated flow switch. The steam flow switch and the condensate flow switch are connected in a one-out-of-two logic in each of two trip strings. Each of the two trip strings provides input into two trip systems in a one-out-of-two logic, and each trip system isolates either the inboard or outboard IC steam and condensate isolation valves. The IC functions isolate Group 5 valves.
The operability of primary containment instrumentation is dependent on the operability of the individual instrument channel functions specified in Table 3.3.6.1-1. Each function must have a required number of operable channels, with their setpoints within the specified AVs where applicable. Setpoint calibration is in accordance with applicable setpoint methodology assumptions. In general, the individual functions of Table 3.3.6.1-1 are required to be operable in modes 1, 2, and 3, consistent with the applicability of LCO 3.6.1.1, "Primary Containment."
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Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES The isolation signals generated by the primary containment isolation instrumentation are implicitly assumed in safety analyses to limit offsite doses by initiating valve closures. For the purposes of this specification, an IC Steam Flow - High function channel and associated Return Flow - High function channel must be operable (one separate channel for each trip system). Primary containment isolation instrumentation satisfies Criterion 3 of 10 CFR 50.35(c)(2)(ii). The isolation, along with the scram function of the reactor protection system (RPS), ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46. Specific credit for these functions is not assumed in any UFSAR accident analyses since the bounding analysis is performed for large failures such as recirculation system or main steam line breaks (MSLB). However, these instruments prevent the IC steam flow or return flow breaks from becoming bounding.
- 4. TECHNICAL ANALYSIS For this license amendment request, the Safety Analyses, LCOs, and applicability discussions that follow are relevant only to Function 4, IC System Isolation of Table 3.3.6.1-1. Function 4 of Table 3.3.6.1-1 specifies three AVs for IC System Isolation and the following applicable SRs for the existing indicating differential pressure switches.
Table 3.3.6.1-1 Allowable Value Applicable Modes Function 4.a Steam Flow - High *_ 290.76% of rated steam flow 1, 2, 3 Function 4.b Return Flow - High _<30.2 inches water (Unit 2) 1, 2, 3
_<13.7 inches water (Unit 3) 1, 2, 3 Surveillance Requirements Frequency SR 3.3.6.1.2, CHANNEL FUNCTIONAL TEST 92 days SR 3.3.6.1.4, CHANNEL CALIBRATION 92 days SR 3.3.6.1.7, LOGIC SYSTEM FUNCTIONAL TEST 24 months The proposed TS changes support the replacement of a differential pressure switch with a functionally equivalent indicating differential pressure switch. Since there are no functional changes and no change in analytical limits, surveillance requirements and their frequencies remain unchanged.
DNPS proposes to replace existing switches qualified to DOR requirements with switches that are fully qualified to Class 1E requirements. The new switches are qualified to more exacting standards and differ from the existing switches in switch performance values such as reference accuracy and allowed setpoint drift due to accident environment effects. As a result, the calculated AV for the new differential pressure switches differs from that calculated for the existing switches.
The AL is the same for both the existing and proposed replacement switches. The proposed change will not alter the existing circuit design or initiation logic.
The allowable values are chosen low enough to ensure that the trip occurs to prevent fuel damage and maintain the MSLB event as the bounding event. For both the Steam Flow - High and the Return Flow - High, the existing analytical limit of 300% normal flow is retained. For Return Flow -
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I-Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES High, the AV is expressed in engineering units of "inches water," but the underlying AL corresponds to 300% normal flow.
The proposed allowable values remain well above 200% of normal flow. Therefore, lowering the allowable values and corresponding setpoints will have no adverse effect on normal operation of the IC.
The AVs are revised to be consistent with those calculated using the EGC methodology found in NES-EIC-20.04, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy,"
Revision 3. This protocol was previously reviewed and approved by the NRC as part of the Improved Technical Specifications submittal (References 1 and 2). No ALs are changed.
- 5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration According to 10 CFR 50.92, "Issuance of amendment," paragraph (c) a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
In support of this determination, an evaluation of each of the three criteria set forth in 10 CFR 50.92 is provided below regarding the proposed license amendment.
Overview In accordance with 10 CFR 50.90, "Application for amendment of license or construction Permit,"
EGC is requesting a change to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. DPR-19 and DPR-25, for DNPS Units 2 and 3. The proposed change modifies the allowable value (AV) for two primary containment isolation instrumentation functions. Specifically, Isolation Condenser System Isolation Function 4.a, Steam Flow - High and Function 4.b Return Flow - High AVs are revised due to planned replacement of differential pressure switches, currently qualified to Division of Operating Reactors requirements, with switches qualified to Class 1 E requirements. Differences between the two differential pressure switches result in differences in calculated AVs. No analytical value is changed and there are no functional changes.
The proposed TS changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed TS changes support the replacement of a differential pressure switch with a functionally equivalent differential pressure switch. Since there are no functional changes and no Page 4 of 7
r Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES change in analytical limits, there is no significant increase in the probability or consequences of an accident previously evaluated.
Additionally, these changes will not increase the consequences of an accident previously evaluated because the proposed changes do not adversely impact structures, systems, or components.
Furthermore, there will be no change in the types or significant increase in the amounts of any effluents released offsite as a result of the proposed change.
In summary, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed TS changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The change does not adversely impact the manner in which the instrument will operate under normal and abnormal operating conditions. Therefore, these changes provide an equivalent level of safety and will not create the possibility of a new or different kind of accident from any accident previously evaluated. The changes in allowed values do not affect the current safety analysis assumptions. Therefore, these changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed TS changes do not involve a significant reduction in a margin of safety.
The proposed changes do not affect the probability of failure or availability of the affected instrumentation. The revised AVs do not affect the analytical limits assumed in the safety analyses for actuation of instrumentation. Therefore, the proposed changes do not result in a reduction in the margin of safety.
Conclusion Based upon the above evaluation, EGC has concluded that the criteria of 10 CFR 50.92(c) are satisfied and that the proposed TS changes involve no significant hazards consideration: 1) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change, 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.
5.2 Applicable Regulatory RequirementslCriteria Function 4, "Isolation Condenser System Isolation", Functions 4.a, "Steam Flow - High" and 4.b, "Return Flow - High" provide for primary containment isolation and, along with the scram function of the reactor protection system (RPS), ensure that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46. Therefore, the IC Steam Flow - High and Return Flow - High functions must be included in the Dresden Units 2 and 3 TS in accordance with 10 CFR 50.36(c)(2)(ii).
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Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES
- 6. ENVIRONMENTAL CONSIDERATIONS EGC has evaluated these proposed changes in accordance with 10 CFR 51.21, "Criteria for and identification of licensing and regulatory actions requiring environmental assessments." EGC has determined that these proposed changes meet the criteria for a categorical exclusion concurrent with 10 CFR 51.22, "Criterion for categorical exclusion identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," paragraph (c)(9). As such, no irreversible consequences exist in accordance with 10 CFR 50.92, "Issuance of amendment," paragraph (b). This determination is based on the fact that these changes are being proposed as an amendment to a license issued pursuant to 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities," which changes a surveillance requirement (SR), and the amendment meets the following specific criteria:
(1) The proposed changes involve no significant hazards consideration.
As demonstrated in Section 5.1, the proposed changes do not involve a significant hazards consideration.
(2) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
The proposed changes, which revise two allowable values for Isolation Condenser System Isolation, Function 4.a, Steam Flow - High and Function 4.b, Return Flow - High, are consistent with the plant design basis. There is no change to the existing analytical limits for these functions. There will be no significant increase in the amounts of any effluents released offsite. The proposed changes do not result in an increase in power level, do not increase the production, nor alter the flow path or method of disposal of radioactive waste or byproducts. Therefore, the proposed change will not affect the types or increase the amounts of any effluents released offsite.
(3) There is no significant increase in individual or cumulative occupational radiation exposure. I The proposed changes will not result in functional changes in the configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant.
Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
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-t Attachment A DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES
- 7. REFERENCES
- 1. Letter from R. M. Krich (Commonwealth Edison Company) to U. S. NRC, "Request for Technical Specifications Changes for 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, to Implement Improved Standard Technical Specifications," dated March 3, 2000
- 2. Letter from Stewart N. Bailey (U. S. NRC) to 0. D. Kingsley (Exelon), "Issuance of Amendments," dated March 30, 2001 Page 7 of 7
Attachment B MARKED-UP TECHNICAL SPECIFICATIONS PAGE FOR PROPOSED CHANGES REVISED TS PAGE 3.3.6.1-6
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE FUNCTION
- 3. High Pressure Coolant In3ection (HPCI) System Isolation 1.2,3 I F SR 3.3.6.1.2 :5 290.16%
rated steamof
- a. HPCI Steam Line SR Flow-High SR 3.3.6.1.3 flow (Unit 2)
SR 3.3.6.1.6
- 288.23% of 3.3.6.1.7 rated steam flow (Unit 3)
F SR 3.3.6.1.2 ý:3.2 seconds
- b. HPCI Steam Line 1.2,3 SR 3.3.6.1.6 and Flow-Timer SR 3.3.6.1.7 < 8.8 seconds 1.2.3 2 SR SR 3.3.6.1.2 3.3.6.1.3 S104 psig
- c. HPCI Steam Supply Line Pressure-Low SR 3.3.6.1.6 SR 3.3.6.1.7 F SR 3.3.6.1.5 1,2.3 SR 3.3.6.1.6 189°F
- d. HPCI Turbine Area Temperature-High SR 3.3.6.1.7
- 4. Isolation Condenser System Isolation ofoo 1.2.3 F SR SR 3.3.6.1.2 3.3.6.1.4
- a. Steam Flow-High rate steam SR 3.3.6.1.7 flow
<!5 inches F SR 3.3.6.1.2 1.2.3 1 SR 3.3.6.1.4
- b. Return Flow-High SR 3.3.6.1.7 water 1Uit21 I 7 water (Unit 3)
(continued) single trip string.
(a) All four channels must be associated with a 3.3.6.1-6 Amendment No.
Dresden 2 and 3
Attachment C REVISED TECHNICAL SPECIFICATIONS PAGE FOR PROPOSED CHANGES REVISED TS PAGE 3.3.6.1-6
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 3. High Pressure Coolant Injection (HPCI) System Isolation
- a. HPCI Steam Line 1,2,3 1 F SR 3.3.6.1.2 r 290.16% of Flow-High SR 3.3.6.1.3 rated steam SR 3.3.6.1.6 flow (Unit 2)
SR 3.3.6.1.7 : 288.23% of rated steam flow (Unit 3)
- b. HPCI Steam Line 1.2,3 1 F SR 3.3.6.1.2 Ž 3.2 seconds Flow-Timer SR 3.3.6.1.6 and SR 3.3.6.1.7 : 8.8 seconds
- c. HPCI Steam Supply Line 1.2,3 2 F SR 3.3.6.1.2 Ž 104 psig Pressure-Low SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7
- d. HPCI Turbine Area 1,2.3 418) F SR 3.3.6.1.5
- 4. Isolation Condenser System Isolation
- a. Steam Flow-High 1,2,3 1 F SR 3.3.6.1.2
- b. Return Flow-High 1,2,3 1 F SR SR 3.3.6.1.2 3.3.6.1.4
! 26.0 inches water (Unit 2)
II SR 3.3.6.1.7 ! 10.7 inches water (Unit 3)
(continued)
(a) All four channels must be associated with a single trip string.
Dresden 2 and 3 3.3.6.1-6 Amendment No. I