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Category:Letter
MONTHYEARIR 05000261/20240032024-10-30030 October 2024 Integrated Inspection Report 05000261/2024003 ML24297A2182024-10-28028 October 2024 – NRC Operator License IR 05000261/20244022024-10-16016 October 2024 – Security Target Set Baseline Inspection Report 05000261/2024402 IR 05000261/20244012024-09-11011 September 2024 Security Baseline Inspection Report 05000261/2024401 IR 05000261/20240052024-08-22022 August 2024 Updated Inspection Plan for H.B. Robinson Steam Electric Plant - Report 05000261/2024005 ML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area IR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230062024-02-28028 February 2024 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 - Report 05000261-2023006 IR 05000261/20243012024-02-0606 February 2024 – Notification of Licensed Operator Initial Examination 05000261/2024301 ML24033A0592024-02-0202 February 2024 Response to Request for Additional Information 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 IR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 – Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 – Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) 05000261/LER-2023-002, Plant Trip During Reactor Protection System Testing2023-08-17017 August 2023 Plant Trip During Reactor Protection System Testing 05000261/LER-2023-001, Condition Prohibited by Technical Specification Due to Missed Entry Into Limiting Condition for Operation2023-08-10010 August 2023 Condition Prohibited by Technical Specification Due to Missed Entry Into Limiting Condition for Operation IR 05000261/20230022023-08-0707 August 2023 – Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 – Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 – Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 – Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 2024-09-11
[Table view] Category:Safety Evaluation
MONTHYEARML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML21259A0992021-11-0404 November 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21242A2982021-09-21021 September 2021 Proposed Alternative to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21155A2132021-08-26026 August 2021 Plant ML21214A2222021-08-10010 August 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21209A9962021-08-0202 August 2021 Proposed Alternative Request IST-RR-8 Related to the Inservice Testing Program ML21202A3982021-07-27027 July 2021 Relief Request Proposed Alternatives to American Society of Mechanical Engineers Operation and Maintenance Code Isolation Valve Seal Water System ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20097F0882020-06-19019 June 2020 Relief Request RA-19-0106 Regarding Proposed Alternative to ASME Code Case N-729-4 Volumetric or Surface Examination Requirements EPID-L-2019-LLR-0065) ML20058E8992020-06-18018 June 2020 Issuance of Amendment No. 267 Regarding Change to Surveillance Requirement 3.8.2.1 ML20021A0132020-02-19019 February 2020 Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML19205A2892019-09-24024 September 2019 Issuance of Amendment No. 266 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A4822019-06-11011 June 2019 Staff Evaluation the 2017 Annual Report of Changes and Error Corrections Affecting the Large-Break Loss-of-Coolant Accident Analysis ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18115A1502018-05-25025 May 2018 Issuance of Amendment 258 Regarding Request to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (CAC No. MF9544; EPID L-2017-LLA-0206) ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. MF6648, MF6649, MF7693/MF7694) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17039A1532017-03-23023 March 2017 H.B. Robinson, Unit 2 - Issuance of Amendment 250 to Adopt Technical Specification Task Force (TSTF) Change Traveler TSTF-339, Revision 2, "Relocate TS Parameters to the COLR," Consistent with WCAP-14483 (CAC No. MF7615) ML16337A2642017-02-0303 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard 805 2024-08-14
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Text
September 14, 2007 Mr. Thomas D. Walt, Vice President H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550-0790
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - EMERGENCY ACTION LEVEL REVISIONS (TAC NO. MD3327)
Dear Mr. Walt:
By letter dated October 6, 2006, as supplemented by letters dated June 27, 2007, and August 16, 2007, Carolina Power and Light Company, the licensee for the H.B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, now doing business as Progress Energy Carolinas, Inc.,
requested prior U.S. Nuclear Regulatory Commission (NRC) approval for changes to the emergency action levels (EALs) for the plant.
The requested changes to the licensees EALs support a conversion from the current EAL scheme to a system based on the Nuclear Energy Institutes (NEI) Letter 99-01, Methodology for Development of Emergency Action Levels (Revision 4, January 2003), in accordance with Regulatory Issue Summary 2003-18, including Supplements 1 and 2, Use of NEI 99-01, Methodology for Development of Emergency Action Levels. HBRSEP currently uses an EAL scheme based on NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
The NRC staff has completed a technical and regulatory review of the proposed EAL changes and supporting documentation. The staff has concluded that incorporation of the proposed changes does not decrease the effectiveness of the applicable Emergency Plans, and that the plans, as changed, continue to meet the standards of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.47, Emergency Plans, paragraph (b), and the requirements of Appendix E to 10 CFR Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities.
T.D. Walt The basis for the staffs conclusion is contained in the attached safety evaluation. If you have any questions, please contact me 301-415-3178.
Sincerely,
/RA/
Marlayna Vaaler, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-261
Enclosure:
Safety Evaluation cc w/enclosure: See next page
T.D. Walt The basis for the staffs conclusion is contained in the attached safety evaluation. If you have any questions, please contact me 301-415-3178.
Sincerely,
/RA/
Marlayna Vaaler, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-261
Enclosure:
Safety Evaluation cc w/enclosure: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl2-2(TBoyce)
LPL2-2 R/F RidsNrrPMMVaaler (hard copy)
EWeiss, NSIR RidsNrrLACSola (hard copy)
MNorris, NSIR RidsRgn2MailCenter (RMusser)
RidsAcrsAcnwMailCenter RidsOgcRp Accession Number: ML072540561 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA NSIR/LIB/BC LPL2-2/BC NAME MVaaler CSola EWeiss* SBailey for TBoyce DATE 09/10/07 09/13/07 9/4/2007 09/14/07
- by memo dated OFFICIAL RECORD COPY
Mr. T. D. Walt H. B. Robinson Steam Electric Plant, Carolina Power & Light Company Unit No. 2 cc:
David T. Conley Mr. C. T. Baucom Associate General Counsel II - Legal Supervisor, Licensing/Regulatory Programs Department H. B. Robinson Steam Electric Plant, Progress Energy Service Company, LLC Unit No. 2 Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602-1551 3581 West Entrance Road Hartsville, South Carolina 29550 Ms. Margaret A. Force Assistant Attorney General Ms. Beverly Hall, Section Chief State of North Carolina N.C. Department of Environment Post Office Box 629 and Natural Resources Raleigh, North Carolina 27602 Division of Radiation Protection 3825 Barrett Dr.
U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27609-7721 Resident Inspectors Office H. B. Robinson Steam Electric Plant Mr. Robert P. Gruber 2112 Old Camden Road Executive Director Hartsville, South Carolina 29550 Public Staff - NCUC 4326 Mail Service Center Mr. Ernest J. Kapopoulos, Jr. Raleigh, North Carolina 27699-4326 Plant General Manager H. B. Robinson Steam Electric Plant, Mr. Henry H. Porter, Assistant Director Unit No. 2 South Carolina Department of Health Carolina Power & Light Company Bureau of Land & Waste Management 3581 West Entrance Road 2600 Bull Street Hartsville, South Carolina 29550 Columbia, South Carolina 29201 Director of Site Operations Mr. J. Paul Fulford H. B. Robinson Steam Electric Plant, Manager, Performance Evaluation and Unit No. 2 Regulatory Affairs PEB 5 Carolina Power & Light Company Carolina Power & Light Company 3581 West Entrance Road Post Office Box 1551 Hartsville, South Carolina 29550 Raleigh, North Carolina 27602-1551 Public Service Commission Mr. John H. ONeill, Jr.
State of South Carolina Pillsbury Winthrop Shaw Pittman, LLP Post Office Drawer 11649 2300 N Street NW.
Columbia, South Carolina 29211 Washington, DC 20037-1128 Ms. J. F. Lucas Manager - Support Services - Nuclear H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO PROPOSED REVISIONS OF THE EMERGENCY ACTION LEVELS FOR THE H. B. ROBINSON STEAM ELECTRIC PLANT DOCKET NO. 50-261
1.0 INTRODUCTION
By letter dated October 6, 2006 (Reference No. 1), as supplemented by letters dated June 27, 2007, and August 16, 2007 (Reference Nos. 2 and 3), Carolina Power and Light Company, the licensee for the H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP), now doing business as Progress Energy Carolinas, Inc. (PEC), requested prior approval from the U.S. Nuclear Regulatory Commission (NRC) for changes to the emergency action levels (EALs) for HBRSEP.
The requested changes to the licensees EALs support a conversion from the current EAL scheme to a system based on the Nuclear Energy Institutes (NEI) Letter 99-01, Methodology for Development of Emergency Action Levels, Revision 4, January 2003 (Reference No. 5), in accordance with Regulatory Issue Summary (RIS) 2003-18, including Supplements 1 and 2, Use of NEI 99-01, Methodology for Development of Emergency Action Levels (Reference No. 6). HBRSEP currently uses an EAL scheme based on NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (Reference No. 4).
2.0 REGULATORY EVALUATION
2.1 Regulations Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.47, Emergency Plans, paragraph (a)(1), states that no operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that the state of onsite and offsite emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. 10 CFR 50.47 also establishes standards that must be met by the onsite and offsite emergency response plans in order for the NRC staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. One of these standards, contained in 10 CFR 50.47(b)(4), stipulates that emergency plans include a standard emergency classification and action level scheme.
Section IV.B, Assessment Actions, to Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, of 10 CFR Part 50 states that emergency plans are to include EALs, which are to be used: 1) as criteria for determining the need for notification and participation of local and State agencies; and 2) for determining when and what type of protective measures should be considered both onsite and offsite to protect public health and
safety. EALs are to be based on in-plant conditions and instrumentation, as well as onsite and offsite monitoring.Section IV.B of Appendix E further states that initial EALs shall be discussed and agreed upon by the applicant and State and local authorities, with approval by the NRC.
The EALs are reviewed annually thereafter with State and local authorities.
In addition,Section IV.B of Appendix E states that an EAL revision must be approved by the NRC before implementation, if it involves: (1) the changing from an EAL scheme based on NUREG-0654/FEMA-REP-1 to a scheme based on NUMARC/NESP-007 or NEI 99-01; (2) the licensee is proposing an alternate method for complying with the regulations; or (3) the EAL revision has been evaluated by the licensee as constituting a decrease in effectiveness.
2.2 Guidance Appendix 1 to NUREG-0654/FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, dated November 1980, describes guidance for developing EALs as required in Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4).
Revision 4 to Regulatory Guide (RG) 1.101, issued in July 2003 (Reference No. 7), endorses the guidance contained in NEI 99-01 as an acceptable alternative method to that given in NUREG-0654/FEMA-REP-1, Appendix 1.
RIS 2003-18 provides guidance for developing or changing a standard emergency classification and action level scheme. In addition, this RIS provides recommendations to assist licensees, consistent with Section IV.B to Appendix E of 10 CFR Part 50, in determining whether to seek prior NRC approval of deviations from the guidance.
3.0 TECHNICAL EVALUATION
HBRSEP currently utilizes an EAL scheme based on NUREG-0654. The proposed changes would allow the licensee to convert to an EAL scheme based on NEI 99-01 in accordance with the guidance from RIS 2003-18. The proposed changes also include the addition of a new EAL based on low lake level (EAL HU1.6) and the correction of a voltage threshold value for EAL CU1.2 as provided in Reference No. 3. These changes were submitted to the NRC for a technical and regulatory review prior to implementation, as required under Section IV.B of Appendix E to 10 CFR Part 50.
The staff reviewed the proposed revisions to the EALs against the guidance in NEI 99-01 to determine if the changes meet the following guidelines:
- 1. consistency (i.e., the proposed EALs would lead to similar decisions under similar circumstances at different plants);
- 2. human engineering and user friendliness;
- 3. potential for a classification upgrade only when there is an increasing threat to public health and safety;
- 4. ease of upgrading and downgrading;
- 5. thoroughness in addressing, and disposing of, the issues related to completeness and accuracy raised regarding NUREG-0654, Appendix 1;
- 6. technical completeness for each classification level;
- 7. a logical progression in classification for multiple events; and
- 8. objective, observable values.
The NRC staff reviewed the proposed EALs against EALs implemented at other plants of similar design, and has determined that the proposed EALs for HBRSEP are consistent with EALs implemented at other plants, use objective and observable values, and are consistent with the intent of NEI 99-01. The staff has also determined that the proposed EALs are worded such that human engineering and user friendliness concerns are adequately addressed.
The NRC staff reviewed the proposed EAL sets (a group of EALs within a category related to a common concern, i.e., the Unusual Event, Alert, Site Area Emergency, and General Emergency related to a failure of the plant to shutdown via an automatic scram, would be considered an EAL set), and has determined that classification upgrades are based upon an increasing threat to public health and safety. The staff also determined that the EAL sets can effectively support upgrading and downgrading, follow a logical progression for multiple events, and are in accordance with the intent of NEI 99-01.
The NRC staff reviewed the proposed EALs for technical completeness and accuracy and has determined that the proposed EALs are consistent with NEI 99-01, which was determined to be an acceptable alternative to EALs contained in NUREG-0654, Appendix 1.
4.0 CONCLUSION
The NRC staff performed a technical and regulatory review of the proposed changes to the HBRSEP EALs. The staff has determined that incorporation of the proposed EAL changes does not decrease the effectiveness of the applicable Emergency Plans, and that the plans, as changed, continue to meet the standards of 10 CFR Section 50.47(b) and the requirements of Appendix E to 10 CFR Part 50. The conclusions of this safety evaluation are specific to the EALs and EAL Technical Basis Document provided in Reference No. 2, to also include the addition of a new EAL based on low lake level (EAL HU1.6) and the correction of a voltage threshold value for EAL CU1.2, as provided in Reference No. 3.
The staff has determined, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the proposed emergency plan changes will not be inimical to the common defense and security or to the health and safety of the public. The proposed changes to the HBRSEP EALs are therefore acceptable to the NRC staff.
5.0 REFERENCES
- 1. Letter from Progress Energy Carolinas, Inc., to the NRC dated October 6, 2006, Request for Review and Approval of Proposed Changes to Emergency Action Levels.
Agencywide Documents Access and Management System (ADAMS) Accession No. ML062890071. ADAMS Package Accession No. ML062890070.
- 2. Letter from Progress Energy Carolinas, Inc., to the NRC dated June 27, 2007, Response to NRC Request for Additional Information Regarding Proposed Revisions to the Emergency Action Levels. ADAMS Accession No. ML071860398.
- 3. Letter from Progress Energy Carolinas, Inc., to the NRC dated August 16, 2007, Response to NRC Request for Additional Information Regarding Proposed Revisions to the Emergency Action Levels. ADAMS Accession No. ML072350354. ADAMS Package Accession No. ML072350356.
- 4. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. ADAMS Accession No. ML040420012.
- 5. NEI 99-01, Methodology for Development of Emergency Action Levels, Revision 4, January 2003. ADAMS Accession No. ML041470143.
- 6. Regulatory Issue Summary 2003-18, with Supplements 1 & 2, Use of NEI 99-01, Methodology for Development of Emergency Action Levels. ADAMS Accession Nos.
ML032580518, ML041550395, and ML051450482.
- 7. Regulatory Guide 1.101, Emergency Planning and Preparedness for Nuclear Power Reactors, Revision 4. ADAMS Accession No. ML032020276.
Principal Contributor: Michael Norris Date: September 14, 2007