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Category:Letter type:RA
MONTHYEARRA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024
Submittal of 2023 Sea Turtle Annual Report
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-23-0284, 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-23-0225, 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-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023
Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner
RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023
License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .
RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 262023-06-28028 June 2023
Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26
RA-23-0145, Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks2023-06-15015 June 2023
Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks
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-23-0139, Registration for Use of General License Spent Fuel Casks2023-06-0606 June 2023
Registration for Use of General License Spent Fuel Casks
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-23-0044, 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-23-0096, Post Accident Monitoring (PAM) Instrumentation Report2023-04-12012 April 2023
Post Accident Monitoring (PAM) Instrumentation Report
RA-23-0063, Notification of Deviation from BWRVIP Guidelines2023-04-11011 April 2023
Notification of Deviation from BWRVIP Guidelines
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-23-0021, Unit 2 Cycle 26 Core Operating Limits Report (COLR)2023-02-22022 February 2023
Unit 2 Cycle 26 Core Operating Limits Report (COLR)
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-23-0010, 2022 Sea Turtle Annual Report2023-01-0909 January 2023
2022 Sea Turtle Annual Report
RA-22-0616, Revision to Brunswick Snubber Program Plan2023-01-0505 January 2023
Revision to Brunswick Snubber Program Plan
RA-22-0308, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2022-12-16016 December 2022
Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner
RA-22-0342, Revision to Emergency Plan On-Shift Staffing Analysis2022-12-0808 December 2022
Revision to Emergency Plan On-Shift Staffing Analysis
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-22-0344, Notification of Deviation from BWRVIP Guidelines2022-11-30030 November 2022
Notification of Deviation from BWRVIP Guidelines
RA-22-0261, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2022-09-15015 September 2022
Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks
RA-22-0271, Accident Monitoring Instrumentation Special Report2022-09-13013 September 2022
Accident Monitoring Instrumentation Special Report
RA-22-0252, Registration for Use of General License Spent Fuel Casks2022-08-25025 August 2022
Registration for Use of General License Spent Fuel Casks
RA-22-0190, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR .2022-08-11011 August 2022
Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR .
RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022
Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24
RA-22-0175, Post Accident Monitoring (PAM) Instrumentation Report2022-06-0101 June 2022
Post Accident Monitoring (PAM) Instrumentation Report
RA-22-0155, Revision to Emergency Plan Annex and Implementing Procedure2022-05-26026 May 2022
Revision to Emergency Plan Annex and Implementing Procedure
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022
Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data
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-22-0029, 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-22-0028, 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-22-0114, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory2022-04-0101 April 2022
Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory
RA-22-0095, Unit 1 Cycle 24 Core Operating Limits Report (COLR)2022-03-29029 March 2022
Unit 1 Cycle 24 Core Operating Limits Report (COLR)
RA-22-0110, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-03-25025 March 2022
Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.
RA-22-0014, Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations2022-03-21021 March 2022
Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022
Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative
RA-22-0046, Withdrawal of One-Time Exemption from 10 CFR 50, Appendix E, Section IV.F.2.d2022-01-31031 January 2022
Withdrawal of One-Time Exemption from 10 CFR 50, Appendix E, Section IV.F.2.d
RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022
Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
2024-01-10
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Text
John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 o: 910.832.3698 December 17, 2019 Serial: RA-19-0446 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 Request to Correct Administrative Technical Specification Error
References:
- 1. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program," dated December 21, 2015, ADAMS Accession Number ML16004A249
- 2. Letter from Andrew Hon (NRC) to William R. Gideon (Duke Energy), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments Regarding Request to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program," dated May 24, 2017, ADAMS Accession Number ML17096A129
- 3. SECY-96-238, "Proposed Guidance for Correction of Technical Specification Typographical Errors," ADAMS Accession Number 9611250030 (Legacy Library)
- 4. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission, "Request for License Amendment Regarding Core Flow Operating Range Expansion," dated September 6, 2016, ADAMS Accession Number ML16257A410
- 5. Letter from Andrew Hon (NRC) to William R. Gideon (Duke Energy), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendment Regarding Core Flow Operating Range Expansion (MELLLA+), dated September 18, 2018, ADAMS Accession Number ML18172A258 Ladies and Gentlemen:
Duke Energy Progress, LLC (Duke Energy), requests a correction of an error in the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit No. 2. The error was inadvertently introduced by issuance of Amendment 304 for Unit 2 on May 24, 2017 (i.e.,
Reference 2). The error was not noticed to the public, nor reviewed by the NRC as part of the application amendment process (i.e., Reference 1), and thus falls within the scope of guidance provided in SECY-96-238 (i.e., Reference 3). The affected page was re-issued with Amendment 313 for Unit 2 on September 18, 2018 (i.e. Reference 5). Again, the error was not noticed to the public, nor reviewed by the NRC as part of the application amendment process (i.e., Reference 4).
RA-19-0446 Enclosure 1 Page 1 of 2 Description of Technical Specification Error Requested Action Consistent with the information contained in SECY-96-238, "Proposed Guidance for Correction of Technical Specification Typographical Errors," Duke Energy Progress, LLC (Duke Energy),
requests a correction of an error in the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit No. 2.
Typographical Error On December 21, 2015 (i.e., Reference 1), Duke Energy submitted a license amendment request (LAR) to adopt Technical Specification Task Force (TSTF) Standard Technical Specifications (STS) Change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b," Revision 3. Surveillance Requirement (SR) 3.3.1.1.18 was not impacted by the requested LAR. However, SR 3.3.1.1.16 and SR 3.3.1.1.17 which appear on the affected page (i.e., Unit 2 page 3.3-7) were revised. The mark-up of page 3.3-7 did not alter SR 3.3.1.1.18 which stated:
Adjust recirculation drive flow to conform to reactor core flow.
The wording of SR 3.3.1.1.18 was inadvertently changed when typed pages were provided in support of issuance of the proposed LAR. SR 3.3.1.1.18, as issued in Amendment 304 for Unit 2 (i.e., Reference 2), now states:
Adjust the flow control trip reference card to conform to reactor flow.
On September 6, 2016 (i.e., Reference 3), Duke Energy submitted a LAR to expand the core flow operating range. As part of this LAR, SR 3.3.1.1.19 was deleted. Again, SR 3.3.1.1.18 was not impacted by the requested LAR and the TS mark-ups supporting the LAR did not include SR 3.3.1.1.18. On September 18, 2018 (i.e., Reference 4) Unit 2 page 3.3-8 was issued in Amendment 313 for Unit 2, indicating deletion of SR 3.3.1.1.19, with the incorrect wording of SR 3.3.1.1.18 remaining.
Correction to the Affected TS Page SECY- 96-238 (i.e., Reference 5) provides guidance for correction of inadvertent typographical errors in the TSs. It states, in part:
the case in which the staff or licensee can demonstrate that the error was introduced inadvertently in a particular license amendment and that the erroneous change was not addressed in the notice to the public nor reviewed by the staff. Under these limited circumstances, the change that introduced the typographical error was not a proper amendment to the license because it was neither addressed in the notice nor reviewed, and correction of the typographical error is not a "change" to the TSs. Accordingly, the typographical error may be corrected by a letter to the licensee from the NRC staff, instead of an amendment to the license.
The above error was not noticed to the public, nor was it reviewed by the NRC as part of the amendment process. The pre-notice for Amendment 304 was published in the Federal Register on March 29, 2016 (i.e., 81 FR 17504), and the pre-notice for Amendment 313 was published in the Federal Register on January 3, 2017 (i.e., 82 FR 158). Neither discussed revising
RA-19-0446 Enclosure 1 Page 2 of 2 SR 3.3.1.1.18. Similarly, the LARs supporting Amendments 304 and 313 did not indicate any change to SR 3.3.1.1.18. Therefore, this error may be corrected without a license amendment. provides a mark-up of the affected TS page as issued by Amendment 313. provides a revised (i.e., typed) copy of the TS page.
References
- 1. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program," dated December 21, 2015, ADAMS Accession Number ML16004A249
- 2. Letter from Andrew Hon (NRC) to William R. Gideon (Duke Energy), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments Regarding Request to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program," dated May 24, 2017, ADAMS Accession Number ML17096A129
- 3. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission, "Request for License Amendment Regarding Core Flow Operating Range Expansion," dated September 6, 2016, ADAMS Accession Number ML16257A410
- 4. Letter from Andrew Hon (NRC) to William R. Gideon (Duke Energy), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendment Regarding Core Flow Operating Range Expansion (MELLLA+), dated September 18, 2018, ADAMS Accession Number ML18172A258
- 5. SECY-96-238, "Proposed Guidance for Correction of Technical Specification Typographical Errors," ADAMS Accession Number 9611250030 (Legacy Library)
RA-19-0446 Enclosure 2 Mark-up of Affected Technical Specification Page
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.16 Verify Turbine Stop ValveClosure and Turbine In accordance with Control Valve Fast Closure, Trip Oil PressureLow the Surveillance Functions are not bypassed when THERMAL Frequency Control POWER is 26% RTP. Program SR 3.3.1.1.17 --------------------------------NOTES----------------------------
- 1. Neutron detectors are excluded.
- 2. For Functions 3 and 4, the sensor response time may be assumed to be the design sensor response time.
Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.18 Adjust recirculation drive flow to conform to reactor Once within 7 days core flow.Adjust the flow control trip reference card to after reaching conform to reactor flow. equilibrium conditions following refueling outage Brunswick Unit 2 3.3-8 Amendment No. 313
RA-19-0446 Enclosure 3 Revised (Typed) Technical Specification Page
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.16 Verify Turbine Stop ValveClosure and Turbine In accordance with Control Valve Fast Closure, Trip Oil PressureLow the Surveillance Functions are not bypassed when THERMAL Frequency Control POWER is 26% RTP. Program SR 3.3.1.1.17 --------------------------------NOTES----------------------------
- 1. Neutron detectors are excluded.
- 2. For Functions 3 and 4, the sensor response time may be assumed to be the design sensor response time.
Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.18 Adjust recirculation drive flow to conform to reactor Once within 7 days core flow. after reaching equilibrium conditions following refueling outage Brunswick Unit 2 3.3-8 Amendment No. 313
