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Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024
Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report
RA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024
Submittal of 2023 Sea Turtle Annual Report
RA-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-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024
Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX
RA-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024
Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval
RA-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024
10 CFR 50.54(q) Evaluation
RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023
Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation
RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023
Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency
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-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023
Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency
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-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023
Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)
RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023
Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific
RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023
Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power
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-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023
Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)
RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023
License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area
RA-23-0268, Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan2023-09-29029 September 2023
Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan
RA-23-0234, Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)2023-09-28028 September 2023
Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)
RA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023
Refuel 27 (C1 R27) Inservice Inspection (ISI) Report
RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023
Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals
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-23-0228, Registration for Use of General License Spent Fuel Cask Number 1752023-09-14014 September 2023
Registration for Use of General License Spent Fuel Cask Number 175
RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023
License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology
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-23-0223, Registration for Use of General License Spent Fuel Cask Numbers 173 and 1742023-08-23023 August 2023
Registration for Use of General License Spent Fuel Cask Numbers 173 and 174
RA-23-0222, On-Shift Staffing Analysis (Ossa), Revision 12023-08-23023 August 2023
On-Shift Staffing Analysis (Ossa), Revision 1
RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023
Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks
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-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023
Reply to a Notice of Violation (NOV) 05000270/2023010-02
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-23-0154, 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-23-0136, 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-23-0195, Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)2023-07-20020 July 2023
Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)
RA-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)2023-07-18018 July 2023
Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
RA-23-0184, Registration for Use of General License Spent Fuel Cask Numbers 171 and 1722023-07-10010 July 2023
Registration for Use of General License Spent Fuel Cask Numbers 171 and 172
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-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023
10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record
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-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023
Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)
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-23-0145, 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-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023
Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2
RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023
License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications
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
2024-02-05
[Table view] |
Text
Regis T. Repko 526 South Church Street Charlotte, NC 28202 Mailing Address:
Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 704-382-4126 704-382-6056 fax Serial: RA-15-0049 December 21, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 / RENEWED LICENSE NOS. DPR-71 AND DPR-62 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 / RENEWED LICENSE NOS. NPF-35 AND NPF-52 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 / RENEWED LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 / RENEWED LICENSE NOS. DPR-38, DPR-47 AND DPR-55
SUBJECT:
COMMITMENT TO MAINTAIN SEVERE ACCIDENT MANAGEMENT GUIDELINES The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 (BSEP); Shearon Harris Nuclear Power Plant, Unit 1 (HNP); H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP); Catawba Nuclear Station, Units 1 and 2 (CNS); McGuire Nuclear Station, Units 1 and 2 (MNS); and Oconee Nuclear Station, Units 1, 2, and 3 (ONS). These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures (EOPs). SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments are listed in the Attachment.
It is expected that NRC staff personnel will conduct periodic inspection of our SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. We
U.S. Nuclear Regulatory Commission RA-15-0049 Page2 also understand that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.
Regis T. Repko Sr. Vice President - Governance, Projects, and Engineering MKL
Attachment:
List of Regulatory Commitments cc: (all with Attachment)
USNRC Region II USN RC Resident Inspector - BSEP USN RC Resident Inspector - HNP USN RC Resident Inspector - RNP USN RC Resident Inspector - CNS USNRC Resident Inspector - MNS USNRC Resident Inspector - ONS A. Hon, NRA Project Manager - BSEP M. C. Barillas, NRA Project Manager - HNP & RNP G. E. Miller, NRA Project Manager - CNS & MNS J. R. Hall, NRA Project Manager - ONS D. Young, NEI (dly@nei.org)
U.S. Nuclear Regulatory Commission RA-15-0049 Attachment Page 1 of 2 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Brunswick Steam Electric Plant, Unit Nos. 1 and 2 (BSEP); Shearon Harris Nuclear Power Plant, Unit 1 (HNP); H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP); Catawba Nuclear Station, Units 1 and 2 (CNS); McGuire Nuclear Station, Units 1 and 2 (MNS); and Oconee Nuclear Station, Units 1, 2, and 3 (ONS) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 1 For BSEP, HNP, RNP, CNS, X October 31, 2016 MNS, and ONS, SAMGs will be considered within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
2 The BSEP SAMG will be X June 30, 2017 updated to revision 3 of the BWROG generic severe accident guidelines (published February, 2013).
3 The HNP, RNP, CNS, MNS, and X Within 2 refueling ONS SAMGs will be updated to outages or 3 years future revisions of the PWROG of the publication generic severe accident technical date of the guidelines, and the SAMGs will guidelines, be integrated with other whichever is emergency response guideline greater sets and symptom-based Emergency Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
U.S. Nuclear Regulatory Commission RA-15-0049 Attachment Page 2 of 2 TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 4 The BSEP SAMG will be updated X Within 2 refueling to future revisions of the BWROG outages or 3 years generic severe accident technical of the publication guidelines, and the SAMG will be date of the integrated with other emergency guidelines, response guideline sets and whichever is symptom-based Emergency greater Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents. Note: For BSEP, use of NEI 14-01 guidance begins with the update to revision 4 of the BWROG generic severe accident guidelines.
Regis T. Repko 526 South Church Street Charlotte, NC 28202 Mailing Address:
Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 704-382-4126 704-382-6056 fax Serial: RA-15-0049 December 21, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 / RENEWED LICENSE NOS. DPR-71 AND DPR-62 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 / RENEWED LICENSE NOS. NPF-35 AND NPF-52 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 / RENEWED LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 / RENEWED LICENSE NOS. DPR-38, DPR-47 AND DPR-55
SUBJECT:
COMMITMENT TO MAINTAIN SEVERE ACCIDENT MANAGEMENT GUIDELINES The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 (BSEP); Shearon Harris Nuclear Power Plant, Unit 1 (HNP); H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP); Catawba Nuclear Station, Units 1 and 2 (CNS); McGuire Nuclear Station, Units 1 and 2 (MNS); and Oconee Nuclear Station, Units 1, 2, and 3 (ONS). These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures (EOPs). SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments are listed in the Attachment.
It is expected that NRC staff personnel will conduct periodic inspection of our SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. We
U.S. Nuclear Regulatory Commission RA-15-0049 Page2 also understand that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.
Regis T. Repko Sr. Vice President - Governance, Projects, and Engineering MKL
Attachment:
List of Regulatory Commitments cc: (all with Attachment)
USNRC Region II USN RC Resident Inspector - BSEP USN RC Resident Inspector - HNP USN RC Resident Inspector - RNP USN RC Resident Inspector - CNS USNRC Resident Inspector - MNS USNRC Resident Inspector - ONS A. Hon, NRA Project Manager - BSEP M. C. Barillas, NRA Project Manager - HNP & RNP G. E. Miller, NRA Project Manager - CNS & MNS J. R. Hall, NRA Project Manager - ONS D. Young, NEI (dly@nei.org)
U.S. Nuclear Regulatory Commission RA-15-0049 Attachment Page 1 of 2 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Brunswick Steam Electric Plant, Unit Nos. 1 and 2 (BSEP); Shearon Harris Nuclear Power Plant, Unit 1 (HNP); H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP); Catawba Nuclear Station, Units 1 and 2 (CNS); McGuire Nuclear Station, Units 1 and 2 (MNS); and Oconee Nuclear Station, Units 1, 2, and 3 (ONS) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 1 For BSEP, HNP, RNP, CNS, X October 31, 2016 MNS, and ONS, SAMGs will be considered within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
2 The BSEP SAMG will be X June 30, 2017 updated to revision 3 of the BWROG generic severe accident guidelines (published February, 2013).
3 The HNP, RNP, CNS, MNS, and X Within 2 refueling ONS SAMGs will be updated to outages or 3 years future revisions of the PWROG of the publication generic severe accident technical date of the guidelines, and the SAMGs will guidelines, be integrated with other whichever is emergency response guideline greater sets and symptom-based Emergency Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
U.S. Nuclear Regulatory Commission RA-15-0049 Attachment Page 2 of 2 TYPE (Check One) SCHEDULED COMMITMENT ONE- COMPLETION CONTINUING DATE/EVENT TIME COMPLIANCE ACTION 4 The BSEP SAMG will be updated X Within 2 refueling to future revisions of the BWROG outages or 3 years generic severe accident technical of the publication guidelines, and the SAMG will be date of the integrated with other emergency guidelines, response guideline sets and whichever is symptom-based Emergency greater Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents. Note: For BSEP, use of NEI 14-01 guidance begins with the update to revision 4 of the BWROG generic severe accident guidelines.
