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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML22307A1152022-11-28028 November 2022 Authorization of Relief Request No. 10 Part II Related to Repair of Intake Cooling Water Discharge Piping (EPID L-2022-LLR-0032) (Non-Proprietary) ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18071A0802018-04-0606 April 2018 Correction to Safety Evaluation for Amendment Nos. 278 and 273 Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML16335A1952017-02-14014 February 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Pumps ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16279A4552016-10-28028 October 2016 Turkey Point Nuclear Generating Station Units 3 & 4 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML16011A4402016-02-0101 February 2016 Safety Evaluation for Relief Request No. 2 for the Fifth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations of the Regenerative Heat Exchanger Welds (MF6384-MF6385) ML16011A2052016-01-22022 January 2016 Safety Evaluation for Relief Request No. PR-02, for the Fifth 10-Year Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Residual Heat Removal Pumps (CAC Nos. MF6388 & MF6389) ML15350A2032015-12-23023 December 2015 Safety Evaluation for Relief Request No. 16, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A1082015-12-0909 December 2015 Safety Evaluation for Relief Request No. PR-01, for the Fifth 10-Yeaer Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Boric Acid Transfer Pumps ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15271A3252015-10-14014 October 2015 Safety Evaluation for Relief Request No. 1, Revision 1 for Fifth 10-Year Inservice Inspection Interval - Repair of Pressurizer Stainless Steel Heater Sleeve Without Flaw Removal ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses 2024-01-22
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 December 14, 2009 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 TURKEY POINT, UNITS 3 AND 4 -EVALUATION OF PROPOSED EMERGENCY ACTION LEVEL REVISION (TAC NOS. MD9924 AND MD9925)
Dear Mr. Nazar:
By letter dated May 14, 2009, as supplemented by letters dated May 27 and June 16, 2009, Florida Power and Light (the licensee) requested prior U.S. Nuclear Regulatory Commission (NRC) approval for proposed changes to the emergency action levels (EALs) for the Turkey Point Nuclear Power Station. The requested changes to the licensee's EALs support a conversion from the current EAL scheme to a scheme based on Nuclear Energy Institute (NEI) 99-01, "Methodology for Development of Emergency Action Levels" (Revision 5, February 2008). Turkey Point 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 performed a review of the proposed changes to Turkey Point's EALs as directed by Appendix E to Title 10 of the Code of Federal Regulations (10 CFR) Part 50. The NRC staff determined that incorporation of the proposed changes meets the standards in 10 CFR.50.47(b) and the requirements of Appendix E t010 CFR Part 50, and provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Therefore, the NRC staff concludes that the licensee's proposed changes to the EALs for Turkey Point, as outlined in its application dated May 14, 2008, as supplemented by letters dated May 27 and June 16, 2009, are acceptable.
M. Nazar -2 The licensee will implement the EALs by May 31, 2010, which includes the implementation of the Emergency Action Level Design Basis Document.
If the licensee changes the EALs as approved by the enclosed Safety Evaluation via 10 CFR 50.54(q) prior to implementation, the licensee shall ensure that the changes are provided to the NRC during the next Emergency Preparedness baseline inspection.
Sincerely, hv Eric J. Leeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-250 and Safety cc w/encl:
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REGARDING THE PROPOSED REVISION TO EMERGENCY ACTION LEVELS FLORIDA POWER AND LIGHT COMPANY, ET AL. TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By letter dated May 14, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081420474), as supplemented by letters dated May 27 and June 16, 2009 (ADAMS Accession Nos. ML091600594 and ML091750167 respectively), Florida Power and Light (the licensee) requested prior U.S. Nuclear Regulatory Commission (NRC) approval for proposed changes to the emergency action levels (EALs) for the Turkey Point Plant. The requested changes to the licensee's EALs support a conversion from the current EAL scheme to a scheme based on Nuclear Energy Institute (NEI) 99-01 J "Methodology for Development of Emergency Action Levels" (Revision 5, February 2008). Turkey Point 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.7).
2.0 REGULATORY EVALUATION
The NRC staff reviewed the proposed revision against the regulations and guidance described below. 2.1 Regulations Section 47 of Part 50, "Domestic Licensing of Production and Utilization Facilities," in Title 10 of the Code of Federal Regulations (10 CFR) sets forth emergency plan requirements for nuclear power plant facilities.
Paragraph 50.47(a)(1
)(i) states, in part, "... no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency." Paragraph 50.47(b) establishes the standards that the on-site and offsite emergency response plans must meet for 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,1 0 CFR 50.47(b)(4), stipulates that emergency plans include a standard emergency classification and action level scheme. Enclosure
-2 Section IV.B of Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," to 10 CFR Part 50, states, in part, The means to be used for determining the magnitude of, and for continually assessing the impact of, the release of radioactive materials shall be described, including emergency action levels that are to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and outside the site boundary to protect health and safety. The emergency action levels shall be based on in-plant conditions and instrumentation in addition to onsite and offsite monitoring.
These initial emergency action levels shall be discussed and agreed on by the applicant or licensee and state and local governmental authorities, and approved by the NRC. Thereafter, emergency action levels shall be reviewed with the State and local governmental authorities on an annual basis. A revision to an emergency action level must be approved by the NRC before implementation if: (1) The licensee is changing from one emergency action level scheme to another emergency action level scheme (e.g., a change from an emergency action level scheme based on NUREG-0654 to a scheme based upon 007 or NEI-99-01);
(2) The licensee is proposing an alternate method for complying with the regulations; or, (3) The emergency action level revision decreases the effectiveness of the emergency plan. 2.2 Guidance Regulatory Guide 1.101, Revisions 3 and 4, "Emergency Planning and Preparedness for Nuclear Power Reactor," endorsed NUMARC/NESP-007 and NEI 99-01 Revision 4, EAL guidance respectively, as acceptable alternatives to the guidance provided in NUREG-0654 for development of EALs to comply with 10 CFR 50.47 and Appendix E to 10 CFR Part 50. A change in an EAL scheme to incorporate the improvements provided in NUMARC/NESP-007 or NEI 99-01 would not decrease the overall effectiveness of the emergency plan, but due to the potential safety significance of the change, needs prior NRC review and approval.
The NRC staff, in a letter dated February 22, 2008, from Christopher Miller to Alan Nelson, NEI, concluded the guidance contained in t\IEI 99-01, is an acceptable method to develop an EAL scheme that meets the requirements of Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4).
-3 The following are also acceptable methods to the NRC staff for developing EALs that meet the requirements of in Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4): 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; NUMARC/NESP-007, Revision 2, "Methodology for Development of Emergency Action Levels," dated January 1992; and NEI 99-01, Revision 4, "Methodology for Development of Emergency Action Levels," dated January 2003. Guidance is also provided in Regulatory Issue Summary (RIS) 2003-18, with Supplements 1 and 2, "Use of NEI 99-01, Methodology for Development of Emergency Action Levels." This 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.S to Appendix E of Part 50, in determining whether to seek prior NRC approval of deviations from the guidance. TECHNICAL EVALUATION The proposed changes were submitted to the NRC for a technical and regulatory review prior to implementation by the licensee, as required under Section IV.S of Appendix E to 10 CFR Part 50. This evaluation is based on a revision to EALs provided in the licensee's application letter and supplemented by the licensee's responses to the NRC's requests for additional information.
The Turkey Point Nuclear Generating Units 3 and 4 currently utilizes 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.7). The licensee is converting to an EAL scheme based on NEI 99-01, Revision 5, dated February 2008. Henceforth NEI 99-01, Revision 5, dated February 2008 will be referred to as NEI 99-01. In its application and supplemental letters, the licensee submitted the proposed EALs for Turkey Point, their technical basis, a comparison matrix, the EAL numbering scheme, and an explanation for any difference or deviation from NEI 99-01. The comparison matrix provided a cross reference relating the proposed EAL scheme to the EALs in NEI 99-01. The NRC staff has reviewed the technical basis for the proposed EALs, the differences or deviations from NEI 99-01, and the licensee's justifications.
The following NEI 99-01 guidelines were considered: consistency (i.e., the EALs would lead to similar decisions under similar circumstances at different plants); human engineering and user-friendliness;
-potential for classification upgrade only when there is an increasing threat to public health and safety; ease of upgrading and downgrading; thoroughness in addressing and disposing of the issues of completeness and accuracy raised regarding Appendix 1 to NUREG-0654; technical completeness of each classification level; logical progression in classification for multiple events; and objective, observable values. The NRC staff reviewed the proposed EALs and has determined that the proposed EALs are consistent with EALs implemented at similarly designed plants, use objective and observable values, and are consistent with the intent of NEI 99-01. The NRC staff reviewed the proposed EALs to determine if they are worded in a manner that addresses human engineering and user friendliness concerns.
The proposed EALs use procedure language, including specific tag numbers for instrument readings and alarms; use flow charts, critical safety function status trees, check lists, and combinations of the above. Based on this review, the staff has determined that the proposed EALs meet the guidelines in NEI 99-01 in this area. The NRC staff reviewed the proposed EAL sets (a group of EALs within a category related to a common concern, that is, the Unusual Event, Alert, Site Area Emergency, and General Emergency related to a failure of the plant to shut down 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, can effectively support upgrading and downgrading, and follow a logical progression for multiple events. Based on this review, the NRC staff concludes that the EALs are in accordance with the intent of NEI 99-01 in these areas. The NRC staff also reviewed the proposed EALs for technical completeness and accuracy for each classification level. The proposed EALs are based on risk assessment to set the boundaries of the emergency classification levels and assure that all EALs that trigger that emergency classification are in the same range of relative risk. Precursor conditions of more serious emergencies also represent a potential risk to the public and are appropriately classified.
The staff has determined that the proposed EALs are consistent with NEI 99-01 in these areas. Based on its review of the proposed EALs, the NRC staff concludes that these EALs are consistent with the guidance in NEI 99-01 in these areas.
-5CONCLUSION The NRC staff performed a technical and regulatory review of the proposed changes to the Turkey Point EALs. The staff has determined that the proposed changes meet the guidelines in NEI 99-01, which is an acceptable alternative for development of an EAL scheme that meets the regulatory requirements.
Based on this, the staff concludes that the proposed EALs meet the standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and provide reasonable assurance that the licensee will take adequate protective measures in a radiological emergency.
Therefore, based on this conclusion, the NRC staff determines that the proposed EAL changes are acceptable. REFERENCES Letter from Florida Power and Light to the NRC, "Change of Emergency Action Levels Basis to NEI 99-01, Revision 5," dated May 14, 2008 (ADAMS Accession No. ML081420474). Letter from Florida Power and Light to the NRC, "Responses to Request for Additional Information Regarding Submittal of NEI 99-01, Revision 5, Based EAL Scheme," dated May 27,2009 (ADAMS Accession No. ML091600594). Letter from Florida Power and Light to the NRC, "Responses to Request for Additional Information Regarding Submittal of NEI 99-01, Revision 5, Based EAL Scheme," dated June 16, 2009 (ADAMS Accession No. ML091750167). NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," February 2008 (ADAMS Accession No. ML080450149). Regulatory Issue Summary 2003-18, with Supplements 1 and 2, "Use of NEI 99-01, Methodology for Development of Emergency Action Levels," January 2003 (ADAMS Accession Nos. ML032580518, ML041550395, and ML051450482). Regulatory Guide 1.101, Revision 4, "Emergency Planning and Preparedness for Nuclear Power Reactors," dated July 2003 (ADAMS Accession No. ML032020276). NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," (ADAMS Accession No. ML040420012). Letter from Christopher Miller, NRC to Alan Nelson, NEI, "US Nuclear Regulatory Commission Review and Endorsement of NEI 99-01," Revision 5, dated February 22, 2008 (ADAMS Accession No. ML080430535).
Principal Contributor:
Don A. Johnson, NSIR Dated: December 14, 2009 M. Nazar The licensee will implement the EALs by May 31,2010, which includes the implementation of the Emergency Action Level Design Basis Document.
If the licensee changes the EALs as approved by the enclosed Safety Evaluation via 10 CFR 50.54(q) prior to implementation, the licensee shall ensure that the changes are provided to the NRC during the next Emergency Preparedness baseline inspection.
Sincerely, IRA by BBoger fori Eric J. Leeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-250 and Safety cc w/encl:
DISTRI BUTION: Public RidsNrrLABClayton Resource RidsRgn2MailCenter Resource LPL2-2 RlF RidsOgcRp Resource RidsNsirDprDdep Resource RidsNrrDorlLpl2-2 Resource RidsAcrsAcnw_MailCTR Resource DJohnson, NSIR RidsNrrDorl Resource RidsNrrOd Resource RidsNrrPMTurkeyPoint Resource RidsNrrAdes Resource RidsNrrAdro Resource ADA MSA N 0.: ML093360321
- b)v memo NRR 106 ccesslon OFFICE NRRlLPL2-2 NRRlLPL2-2/LA NSIRlDPRIDDEP/BC*
NAME JPaige BClayton KWilliams DATE 12/3/09 12/3/09 07/10/09 OFFICE NRRlLPL2-2/BC NRRlDORLlD NRRlD NAME TBoyce JGiitter (AHowe for) ELeeds (BBoger for) DATE 12/10/09 12/11//09 12/14/09 OFFICIAL RECORD