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| The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements. | | The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements. |
| There is no impact on the Technical Specifications. | | There is no impact on the Technical Specifications. |
| The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 1OCFRS0.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval. | | The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 10CFRS0.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval. |
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| To address the obsolescence, maintenance, and reliability concerns the feedwater control system will be upgraded under EC 105814 to replace the pneumatic positioners with digital positioners, provide redundant positioners for the MFCVs, provide capability to switch between the primary and backup MFCV positioners, and replace existing safety-related solenoid valves, including removal of the Wabco quick release valves for the BFCVs. | | To address the obsolescence, maintenance, and reliability concerns the feedwater control system will be upgraded under EC 105814 to replace the pneumatic positioners with digital positioners, provide redundant positioners for the MFCVs, provide capability to switch between the primary and backup MFCV positioners, and replace existing safety-related solenoid valves, including removal of the Wabco quick release valves for the BFCVs. |
| The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements. There is no impact on the Technical Specifications. | | The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements. There is no impact on the Technical Specifications. |
| The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 1OCFR50.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval.}} | | The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 10CFR50.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval.}} |
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Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
[Table view] Category:Test/Inspection/Operating Procedure
[Table view] |
Text
I e{';DUKE
'? ENERGYco Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01 VP I 4800 Concord Road York, SC 29745 o: 803.701.3340 f: 803.701.3221 CNS-17-027 10 CFR 50.59 10 CFR 50.4 May 10, 2017 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Units 1 and 2 Docket Nos.50-413 and 50-414 Renewed License Nos.NPF-35 and NPF-52
Subject:
2015/2016 10 CFR 50.59 Evaluation Summary Report Attached please find the 2015/2016 10 CFR 50.59 Evaluation Summary Report. The report contains a brief description of changes, tests, and experiments, including a summary of the safety evaluations for Catawba Nuclear Station, Units 1 and 2. This report is submitted pursuant to the provisions of 10 CFR 50.59(d)(2) and 10 CFR 50.4.
If there are any questions regarding this submittal, please contact Tolani E. Owusu at (803) 701-5385.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station :eE1:~
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Attachment Catawba Nuclear Station, Units 1 and 2 2015/2016 10 CFR 50.59 Evaluation Summary Report www.duke-energy.com
I U.S. Nuclear Regulatory Commission CNS-17-027 May 10, 2017 Page 2 cc: Attachment C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, NRC Project Manager (Catawba)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852-2738 S. E. Jenkins Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 260 Bull St.
Columbia, SC 29201
..'
U.S. Nuclear Regulatory Commission CNS-17-027 May 10, 2017 Attachment Catawba Nuclear Station, Units 1 and 2 2015/2016 10 CFR 50.59 Evaluation Summary Report
CNS-17-027 May 10, 2017 Page 1of3 Action Request 01351537 EC105813 - Upgrade Unit 1 Main Feedwater Control and Bypass Valve Positioners The present pneumatic valve positioners for the Main Feedwater Control Valves (MFCVs) and Bypass Feedwater Control Valves (BFCVs) are obsolete and present other maintenance and reliability challenges such as susceptibility to drift and absence of ability to communicate with the Distributed Control System (DCS) without additional hardware. Also, single point vulnerabilities exist with the single MFCV pneumatic positioners such that the failure of a single positioner could lead to a unit trip.
To address the obsolescence, maintenance, and reliability concerns the feedwater control system will be upgraded under EC 105813 to replace the pneumatic positioners with digital positioners, provide redundant positioners for the MFCVs, provide capability to switch between the primary and backup MFCV positioners, and replace existing safety-related solenoid valves, including removal of the Wabco quick release valves for the BFCVs.
The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements.
There is no impact on the Technical Specifications.
The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 10CFRS0.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval.
,:,I
Attachment 1 CNS-17-027 May 10, 2017 Page 2 of 3 Action Request 01962944 Revision to Methodology Report DPC-NE-2009-P-A to implement Revision 1-A to WCAP-8963-P-A Addendum 1-A, Safety Analysis for the Revised Fuel Rod Internal Pressure Design Basis (Departure from Nucleate Boiling Mechanistic Propagation Methodology)
The proposed activity being evaluated is a revision to the fuel rod analysis methodology (Section 4.0) in the Westinghouse Fuel Transition methodology report (DPC-NE-2009-P-A). The proposed activity adds a mechanistically based DNB propagation methodology to DPC-NE-2009-P-A. Specifically, methodology report DPC-NE-2009-P-A Revision 3a is being revised to implement Revision 1-A to WCAP-8963-P-A Addendum 1-A, Safety Analysis for the Revised Fuel Rod Internal Pressure Design Basis (Departure from Nucleate Boiling Mechanistic Propagation Methodology),
which has been previously approved by the NRC. DPC-NE-2009 methods are considered part of the Updated Final Safety Analysis Report (UFSAR, Reference 3) via reference, and as such, are considered "as described in the UFSAR." This 10 CFR 50.59 evaluation is performed in accordance with guidance in Revision 1 of NEI 96-07 endorsed by the NRC via Regulatory Guide 1.187. It was concluded that the proposed activity is not a departure from a method of evaluation described in the UFSAR, and thus does not require NRC review and approval.
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Attachment 1 CNS-17-027 May 10, 2017 Page 3 of 3 Action Request 01992138 EC105814/000 - Upgrade Unit 2 Main Feedwater Control and Bypass Valve Positioners The present pneumatic valve positioners for the Main Feedwater Control Valves (MFCVs) and Bypass Feedwater Control Valves (BFCVs) are obsolete and present other maintenance and reliability challenges such as susceptibility to drift and absence of ability to communicate with the Distributed Control System (DCS) without additional hardware. Also, single point vulnerabilities exist with the single MFCV pneumatic positioners such that the failure of a, single positioner could lead to a unit trip.
To address the obsolescence, maintenance, and reliability concerns the feedwater control system will be upgraded under EC 105814 to replace the pneumatic positioners with digital positioners, provide redundant positioners for the MFCVs, provide capability to switch between the primary and backup MFCV positioners, and replace existing safety-related solenoid valves, including removal of the Wabco quick release valves for the BFCVs.
The revised system will continue to perform the same basic function of using a control air signal to modulate control valve position in order to maintain proper steam generator water levels with respect to reactor power output and turbine steam requirements. There is no impact on the Technical Specifications.
The proposed change has been evaluated relative to each of the eight (8) evaluation questions in 10CFR50.59 and the supplemental questions for digital upgrades from NEI 01-01 Appendix A. Considering the probability and consequences of the various hardware and software failure modes of the proposed changes, the evaluation concluded that this change can be implemented without prior NRC approval.