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Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core2023-05-0404 May 2023 Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 42023-04-13013 April 2023 Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0084, Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 42023-03-29029 March 2023 Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 4 RA-23-0083, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 22023-03-16016 March 2023 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0331, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 12022-11-22022 November 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 1 RA-22-0266, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core2022-09-19019 September 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core RA-22-0201, Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-07-21021 July 2022 Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections RA-22-0220, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-19019 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0218, Emergency Action Level (EAL) Technical Basis Document, Revision 32022-07-14014 July 2022 Emergency Action Level (EAL) Technical Basis Document, Revision 3 RA-22-0205, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-11011 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0149, Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-28028 April 2022 Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-22-0029, Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 20212022-04-27027 April 2022 Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 2021 RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 2024-01-10
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Tom Simril
( ., DUKE Vice President ENERGYQt Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York , SC 29745 o: 803.701 .3340 f 803.701 .3221 tom .simril@duke-energy.com RA-21-0283 October 28, 2021 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington , DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket Nos.: 50-413 and 50-414 Commitment Change Evaluation Report for 2020 to October 28, 2021 Regarding the subject report requirement, notification of regulatory commitment changes are provided in Enclosure 1 for Catawba Nuclear Station. This letter is being submitted in accordance with NEI 99-04 , Guidelines for Managing NRC Commitments. This letter informs the NRC of changes in commitments made during the time period from January 1, 2020, through October 28, 2021 .
Questions should be directed to Sherry Andrews, Catawba Regulatory Affairs, at 803-701-3424 .
Sincerely, Tom Simril Vice President, Catawba Nuclear Station Enclosure 1: Catawba Nuclear Station, Notification of Regulatory Commitment Changes www.duke-energy.com
U. S. Nuclear Regulatory Commission October 28, 2021 Page 2 xc:
L. Dudes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 Zachary Stone, NRC Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Zachary.Stone@nrc.gov J. D. Austin, NRC Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Station
Enclosure RA-21-0283 October 28, 2021 Page l 1 Enclosure 1 Catawba Nuclear Station Notification of Regulatory Commitment Changes
Enclosure RA-21-0283 October 28, 2021 Page l 2 Commitment Tracking Number: 02269653-18 Existing Commitment:
In response to NAC Bulletin 2003-01 and to NRC Generic Letter 2004-02, Duke Energy stated that current cleaning practices at Catawba Nuclear Station were as follows from correspondence dated August 7, 2003, found in ADAMS accession number ML032260651, Enclosure II for Catawba Nuclear Station, Item 4:
Current practice at CNS Includes aggressive containment cleaning and cleanliness walkdowns.
CNS outage practices assuring containment cleanliness are described as follows:
- Containment cleaning is conducted prior to Mode 4.
- Extensive containment cleaning is conducted using water spray. In general, wash downs are limited to the space in lower containment that would be submerged under large break LOCA conditions. Accessible floor and wall surfaces and mechanical equipment are washed down.
- Localized washdowns are performed as directed by Radiation Protection.
- Visual inspections are performed on remaining areas of containment. Identified potential debris is cleaned or removed as necessary.
- Containment cleanliness is verified prior to entry into Mode 4 by an Inspection controlled by procedure. This cleanliness inspection ensures that the ECCS sump area is free of debris.
Containment FME controls and inspection activities are implemented during Modes 1 through 4. CNS FME control practices and Inspection activities assuring containment cleanliness during Modes 1 through 4 are described as follows:
- Containment entries during normal power operations are controlled by an administrative procedure. Current process relies on FME and containment cleanliness training, pre-job briefs, and completion of containment access closeout logs.
Increased material accountability control at CNS is planned by requiring material accountability logs be kept for items carried into and out of containment during normal power operations (Modes 1 through 4). These procedural changes will be in place prior to end of the next refueling outage (1 EOC14, Fall 2003)."
Revised Commitment:
Procedural controls governing containment cleanliness and material accountability control to remain the same. Containment will be sprayed down as necessary at the discretion of an SRO with input from Radiation Protection.
Basis for Revision:
Given the current operating practices and procedural controls in place, lower containment spray down does not provide any additional benefit to containment cleanliness. However, procedures will be modified so that spray down can still be performed when deemed necessary by an SRO or as directed by Radiation Protection prior to Mode 4 entry.
Enclosure RA-21-0283 October 28, 2021 Page l 3 Commitment Tracking Number: 02251444-05 Existing Commitment:
Perform the quarterly flush of the RN to CA piping immediately upstream of the RN/CA isolation valves and perform the RN to CA flow measurement test every 18 months on the affected unit.
Revised Commitment:
Perform the quarterly flush of the RN to CA piping immediately upstream of the RN/CA isolation valves.
Basis for Revision:
Commitment Change 2008-C-03 was created to eliminate the original Generic letter 89-13 commitment for the verification of no debris in the Nuclear Service Water System (RN) to the Auxiliary Feedwater System (CA) piping between the RN header and the RN/CA Isolation valve via radiography. The revised commitment included reliance upon the quarterly flush of this short section of piping (PT/1(2)/A/4200/059) and the performance of the RN to CA flow verification test (PT/1 (2)A/4400/014) on an 18-month frequency.
The performance of the dead leg piping flush upstream of the RN/CA isolation valve is performed Immediately prior to the flow verification test to prevent any settled debris from being transported to the CA system. This flush and the quarterly flushes result in the flow verification test providing no benefit in the elimination of debris transport from RN to CA in support of the 2008 commitment change, as the quarterly flush has been proven to be an equally effective and acceptable alternative means to comply with the pipe cleanliness specified by Generic Letter 89-13. The performance of the quarterly flushes on both units performed via PT/1(2)/A/4200/059 has shown no debris in the strainer used In the flush piping.
PT/1(2)A/4400/014 validates the piping roughness parameters assumed in calculation CNC-1223.42-00-0001 (Confirmation of CA System RN Transfer Scheme Adequacy). Previous test results for the previous 4 years show that the system piping between the RN Isolation valve and the CA pump suction has not indicated any fouling. The test results for all four trains of CA are well below the test acceptance line. This test was originally performed when the RN to CA isolation valve was located in the CA pump room which resulted In the piping between the RN valves and CA being filled with raw service water. Station modifications relocated these valves on the same elevation as the main RN supply header. This has allowed the piping downstream of the RN Isolation valves to be filled with condensate grade water which minimizes any potential for fouling that would challenge the assumed piping roughness In the transfer scheme adequacy calculation.
Therefore, the commitment to perform the RN to CA flow verification test as described In the 2008 commitment change can be deleted with the reliance on the RN/CA dead leg flushes which are performed quarterly. In addition, the elimination of the flow verification test from the previous Generic Letter 89-13 does not impact the ability of the RN system to provide emergency cooling water to the CA system.
Enclosure RA-21-0283 October 28, 2021 Page l 4 Commitment Tracking Number: 02092075-07 Existing Commitment:
In response to GL 90-03, Item (b), CP&L and Duke Power described how an adequate vendor interface program for BNP, HNP, RNP, CNS, MNS, and ONS would be maintained which include periodic contact with vendors of key safety-related components (beyond those provided by the NSSS supplier).
Revised Commitment:
The requirement in AD-EG-ALL-1670, Section 5.6 Vendor Re-Contact Program (Revision 0) to periodically contact vendors of critical equipment installed at Duke Energy Nuclear Sites at least every three years to obtain new product information relevant to installed plant equipment will be eliminated.
Basis for Revision:
Based on the continued improvement and maturity of the Operating Experience, Equipment Reliability and Predictive and Preventative Maintenance Programs being implemented across the Duke Fleet, the requirement to periodically re-contact OEM vendors has no significant benefit to nuclear safety. The current Fleet level Programs and Procedures described previously, and other methods of communication with vendors, ensure the reliability of critical SSCs important to nuclear safety.