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Category:Letter type:RA
MONTHYEARRA-24-0208, Refuel 26 (C2R26) Inservice Inspection (ISI) Report2024-08-12012 August 2024 Refuel 26 (C2R26) Inservice Inspection (ISI) Report RA-24-0209, Regulatory Conference, Additional Supporting Information2024-08-0606 August 2024 Regulatory Conference, Additional Supporting Information RA-24-0197, Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition2024-07-31031 July 2024 Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition RA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024 Regulatory Conference Supporting Information RA-24-0092, Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis2024-07-29029 July 2024 Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis RA-24-0165, Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations2024-07-26026 July 2024 Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations RA-24-0178, Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks2024-07-10010 July 2024 Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks RA-24-0172, Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2024-07-0808 July 2024 Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-24-0137, Relief Requests for Inservice Testing Plan – Fifth Interval2024-07-0101 July 2024 Relief Requests for Inservice Testing Plan – Fifth Interval RA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-24-0166, Revision to Emergency Plan Implementing Procedure2024-06-27027 June 2024 Revision to Emergency Plan Implementing Procedure RA-24-0141, Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification2024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification RA-24-0163, Registration for Use of General License Spent Fuel Casks2024-06-19019 June 2024 Registration for Use of General License Spent Fuel Casks RA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 252024-06-19019 June 2024 Inservicee Inspection Program Owners Activity Report Refueling Outage 25 RA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, “Rcs Pressure and Temperature (P/T) Limits”2024-06-18018 June 2024 License Amendment Request Proposing to Revise Technical Specification 3.4.3, “Rcs Pressure and Temperature (P/T) Limits” RA-24-0154, Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-06-0707 June 2024 Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0136, Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 52024-05-24024 May 2024 Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 5 RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-24-0152, Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2024-05-22022 May 2024 Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-24-0132, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report2024-05-14014 May 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical.2024-05-0909 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical. RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0096, Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report2024-04-24024 April 2024 Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0103, Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval2024-04-19019 April 2024 Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0101, (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2024-04-16016 April 2024 (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-24-0117, Cycle 26 Core Operating Limits Report, Revision O2024-04-16016 April 2024 Cycle 26 Core Operating Limits Report, Revision O RA-24-0099, Reactor and Senior Reactor Operator Initial Examination Outlines2024-04-10010 April 2024 Reactor and Senior Reactor Operator Initial Examination Outlines RA-24-0106, Annual Environmental (Non-Radiological) Operating Report2024-04-0909 April 2024 Annual Environmental (Non-Radiological) Operating Report RA-24-0097, Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-04-0303 April 2024 Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0080, Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports2024-03-28028 March 2024 Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports RA-24-0073, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2024-03-21021 March 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-24-0082, Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core2024-03-21021 March 2024 Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process RA-24-0062, 10 CFR 50 .54(q) Evaluation2024-03-0404 March 2024 10 CFR 50 .54(q) Evaluation RA-24-0058, Cycle 25 Core Operating Limits Report (COLR)2024-03-0101 March 2024 Cycle 25 Core Operating Limits Report (COLR) RA-24-0067, Independent Spent Fuel Storage Installation (ISFSI)2024-02-29029 February 2024 Independent Spent Fuel Storage Installation (ISFSI) RA-24-0033, Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2024-02-24024 February 2024 Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-24-0004, End of Cycle 29 (M1R29) Inservice Inspection Summary Report2024-02-21021 February 2024 End of Cycle 29 (M1R29) Inservice Inspection Summary Report RA-24-0053, Registration for Use of General License Spent Fuel Cask Number 1762024-02-20020 February 2024 Registration for Use of General License Spent Fuel Cask Number 176 RA-23-0300, Fifth Ten-Year Inservice Inspection Interval Limited Examinations2024-02-15015 February 2024 Fifth Ten-Year Inservice Inspection Interval Limited Examinations RA-23-0008, Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-02-0606 February 2024 Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-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) 2024-08-06
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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.