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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
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| By letter to the Nuclear Regulatory Commission (NRC) dated December 22, 2009 (Agencywide Documents Access and Management System (ADAMS) (non-public) Accession No. | | By letter to the Nuclear Regulatory Commission (NRC) dated December 22, 2009 (Agencywide Documents Access and Management System (ADAMS) (non-public) Accession No. ML100050503), Exelon Generation Company, LLC (the licensee). submitted a request for NRC review and approval of revisions to the Emergency Plan (EP) Emergency Action Levels (EALs) for the subject plants. The proposed EP changes would incorporate EALs based on the NRC-endorsed methodology Nuclear Energy Institute (NEI) 99-01, Revision (Rev) 5, "Methodology for Development of Emergency Action Levels," dated February 22,2008 (ADAMS Accession No. ML080450149). |
| ML100050503), Exelon Generation Company, LLC (the licensee). submitted a request for NRC review and approval of revisions to the Emergency Plan (EP) Emergency Action Levels (EALs) for the subject plants. The proposed EP changes would incorporate EALs based on the NRC-endorsed methodology Nuclear Energy Institute (NEI) 99-01, Revision (Rev) 5, "Methodology for Development of Emergency Action Levels," dated February 22,2008 (ADAMS Accession No. ML080450149). | |
| By memo dated July 8, 2010 (ADAMS Accession No. ML101890434), the NRC staff concluded that an entire revision from NEI 99-01, Rev. 4 to Rev. 5 is an EAL scheme change that requires prior NRC review and approval per Appendix E to 10 CFR 50. Specifically, EAL scheme changes require approval pursuant to 10 CFR Part 50, Appendix E, Section IV(B)( 1). | | By memo dated July 8, 2010 (ADAMS Accession No. ML101890434), the NRC staff concluded that an entire revision from NEI 99-01, Rev. 4 to Rev. 5 is an EAL scheme change that requires prior NRC review and approval per Appendix E to 10 CFR 50. Specifically, EAL scheme changes require approval pursuant to 10 CFR Part 50, Appendix E, Section IV(B)( 1). |
| In accordance with the requirements of 10 CFR Part 50, Appendix E, Section IV(B)(1), the licensee requested NRC staff review and approval to adopt EALs based on NEt 99-01, Rev 5. | | In accordance with the requirements of 10 CFR Part 50, Appendix E, Section IV(B)(1), the licensee requested NRC staff review and approval to adopt EALs based on NEt 99-01, Rev 5. |
Letter Sequence Acceptance Review |
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TAC:ME3028, (Open) TAC:ME3029, (Open) TAC:ME3030, (Open) TAC:ME3031, (Open) TAC:ME3032, (Open) TAC:ME3033, (Open) TAC:ME3034, (Open) TAC:ME3035, (Open) TAC:ME3036, (Open) TAC:ME3037, (Open) TAC:ME3038, (Open) TAC:ME3039, (Open) TAC:ME3040, (Open) TAC:ME3041, (Open) TAC:ME3042, (Open) TAC:ME3043, (Open) TAC:ME3044, (Open) |
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MONTHYEARML0726804681954-12-31031 December 1954 New Jersey Department of Environmental Protection, Division of Parks and Forestry, State Forest Service, New Jersey'S Big Trees Project stage: Other ML0726705561963-01-31031 January 1963 Us Fish and Wildlife Service, 1963. Distribution of Shellfish Resources in Relation to the New Jersey Intracoastal Waterway -- Manasquan Inlet to Little Egg Harbor. Boston, Ma. January Project stage: Other ML20260G1161965-06-17017 June 1965 Fuel Storage Building Sections & Details. Sheet 1 Project stage: Other ML20260G1231965-08-20020 August 1965 Fuel Storage Building Section & Details. Sheet 7.Field Change Request & Drawing Change Notices Encl Project stage: Other ML20260G1201967-01-31031 January 1967 Fuel Storage Building Sections & Details. Sheet 4 Project stage: Other ML0725407921968-06-0404 June 1968 Drawing 11D-190, 6 Inch Roof Vent. Project stage: Other ML20264B5281971-04-0101 April 1971 Reactor Protection System. Sheet 5 of 13 Project stage: Other ML20206K6391972-05-31031 May 1972 Ack Receipt of Re Technical Basis for Accepting Weld Surface Area W/Bluish Tint.No Further Questions Project stage: Other ML20263J0731972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly a, as-built Project stage: Other ML20263J0711972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly D (48 of 50), as-built Project stage: Other ML20263J0781972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly C Project stage: Other ML20263J0751972-07-18018 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly B (46 of 50), as-built Project stage: Other ML19326C1141972-07-19019 July 1972 SLR Tech Specs from Authority File Project stage: Acceptance Review ML0726405941972-11-17017 November 1972 Jersey Central Power & Light Company, Oyster Creek Nuclear Generating Station Environmental Report, Amendment 2 Project stage: Other ML20263N4591973-01-14014 January 1973 Auxiliary Building Unit 1 Spent Fuel Pool Sections Reinforcing. Sheet 4 Project stage: Other ML20262H5551973-12-14014 December 1973 Watertight Door Assy. Sheet 1 of 3 Project stage: Other ML20262H5581973-12-14014 December 1973 Details:1,2,17 & 21 Thru 27,32,33 & 34. Sheet 2 of 3 Project stage: Other ML20262H5611973-12-14014 December 1973 Details:3,13,19,24,28,35 & 36. Sheet 3 of 3 Project stage: Other ML20263T0291974-04-0909 April 1974 Shore Line Contours. Sheet 3 of 4 Project stage: Other ML20263N4901974-07-15015 July 1974 Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Concrete. Sheet 1 Project stage: Other ML20235X2491974-07-16016 July 1974 Forwards Revised Operator Requalification Program for Plant, Per Recipient 740618 Request Project stage: Other ML20263N4981974-10-10010 October 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Concrete. Sheet 2 Project stage: Other ML20263N4751974-10-11011 October 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 2 Project stage: Other ML0725408181974-10-22022 October 1974 Drawing M-79, Rev. 3, Main Steam Relief Valve Discharge Stack Modification. Project stage: Other ML20263N4621974-11-0505 November 1974 Auxiliary Building Unit 1 Spent Fuel Pool - Sections Reinforcing. Sheet 2 Project stage: Other ML20263N4741974-11-0505 November 1974 Auxiliary Building Unit 2 Spent Fuel Pool Sections Reinforcing. Sheet 3 Project stage: Other ML20263N4671974-11-0505 November 1974 Auxiliary Building Unit 1 Spent Fuel Pool Plan and Sections Reinforcing. Sheet 1 Project stage: Other ML20235X2331974-12-10010 December 1974 Discusses 741206 Meeting W/Util to Review Responsibilities & Outline Scope of Exam for Fuel Handling & Senior Operators at Facility.Addl Info to Develop Written & Operating Test Needed Project stage: Meeting ML20263N4561974-12-13013 December 1974 Auxiliary Building Spent Fuel Pool - Unit 1 Plan and Sections Reinforcing. Sheet 4 Project stage: Other ML20263N4711974-12-13013 December 1974 Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 4 Project stage: Other ML20264B5261975-04-24024 April 1975 Single Line Diagram:125 Volt D-C System Project stage: Other ML0606805861975-05-23023 May 1975 May 23, 1975 - Final Summary Report Startup, Enclosure 4 Project stage: Other ML0607202531975-05-23023 May 1975 May 23, 1975 - Final Summary Report Unit 2 Startup Project stage: Other ML20140F9811975-06-16016 June 1975 Forwards Request for Info Re Ebasco Containment Structures Design Rept,Per 750530 Request.Info for Assessing Design Adequacy of Piping & Mechanical Components Affected by Suppression Pool Dynamic Loadings Needed Project stage: Other ML20235Z6961975-06-17017 June 1975 Requests Listed Info Re Application for Permit to Const Plant,Including Necessary Info to Evaluate Means Employed for Keeping Radioactivity in Effluents to Unrestricted Areas as Low as Practicable,Within 12 Months from 750604 Project stage: Other ML20262H5711975-06-18018 June 1975 Details 2,3,4 & 5. Sheet 3 of 3 Project stage: Other ML20262H5691975-06-18018 June 1975 Details 1 & 6. Sheet 2 of 3 Project stage: Other ML20262H5671975-06-18018 June 1975 4 Ft X 8 Ft Opening Lhrb Door & Frame Assembly. Sheet 1 of 3 Project stage: Other ML20263N4791975-08-15015 August 1975 Auxiliary Building Unit 2 Spent Fuel Pool Plans and Sections Reinforcing. Sheet 1 Project stage: Other ML20236A0651975-10-15015 October 1975 Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days Project stage: Other ML20263N4651975-11-18018 November 1975 Auxiliary Building Spent Fuel Pool - Unit 2 Plan and Sections Reinforcing. Sheet 5 Project stage: Other ML20155J7791976-01-0505 January 1976 Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl Project stage: Other ML20262D8641976-03-26026 March 1976 Piping & Instrumentation Diagram: Type Gs,Oil Piping Diagram Project stage: Other ML20148F2811976-06-0707 June 1976 Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads Project stage: RAI ML20196H3251976-06-29029 June 1976 Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl Project stage: Meeting ML20205H9841976-07-0606 July 1976 Forwards Draft Amends 18 & 23 to Licenses DPR-24 & DPR-27, Respectively, & Safety Evaluation.Amends Revise Tech Specs to Add Surveillance Requirements & Place Limit on Max Weight of Spent Fuel Shipping Cask Used Project stage: Draft Approval ML20245C3281976-07-0909 July 1976 Requests Amend to Fsar,Describing Rupture Discs & Administrative Controls,Tests & Surveillance That Recipient Has or Intends to Have Over Discs,Within 30 Days of Ltr Receipt.Listed Items Should Be in Tech Spec Format Project stage: Other ML20236C3041976-09-14014 September 1976 Notification of 760928 Meeting W/Util in Bethesda,Md to Discuss Util Concepts for Proposed Neutron Shield for Plant. Summary of Neutron Streaming Problem Encl Project stage: Meeting ML20265C7261976-09-17017 September 1976 Elementary Wiring Diagram:Reactor Cooling System Przr Heater Project stage: Other ML20070J8961976-09-29029 September 1976 RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated Project stage: Other 1974-12-13 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:TAC:ME3028]] OR [[:TAC:ME3029]] OR [[:TAC:ME3030]] OR [[:TAC:ME3031]] OR [[:TAC:ME3032]] OR [[:TAC:ME3033]] OR [[:TAC:ME3034]] OR [[:TAC:ME3035]] OR [[:TAC:ME3036]] OR [[:TAC:ME3037]] OR [[:TAC:ME3038]] OR [[:TAC:ME3039]] OR [[:TAC:ME3040]] OR [[:TAC:ME3041]] OR [[:TAC:ME3042]] OR [[:TAC:ME3043]] OR [[:TAC:ME3044]] </code>.
[Table View]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:TAC:ME3028]] OR [[:TAC:ME3029]] OR [[:TAC:ME3030]] OR [[:TAC:ME3031]] OR [[:TAC:ME3032]] OR [[:TAC:ME3033]] OR [[:TAC:ME3034]] OR [[:TAC:ME3035]] OR [[:TAC:ME3036]] OR [[:TAC:ME3037]] OR [[:TAC:ME3038]] OR [[:TAC:ME3039]] OR [[:TAC:ME3040]] OR [[:TAC:ME3041]] OR [[:TAC:ME3042]] OR [[:TAC:ME3043]] OR [[:TAC:ME3044]] </code>. |
Fleet - Acceptance Review Implementation of Emergency Action Level Schemes Developed from NEI 99-01m Rev. 5ML100880085 |
Person / Time |
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Site: |
Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle |
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Issue date: |
07/21/2010 |
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From: |
Nicholas Difrancesco Plant Licensing Branch III |
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To: |
Pacilio M Exelon Nuclear |
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DiFrancesco N, NRR/DORL/LPL3-2, 415-1115 |
References |
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TAC ME3028, TAC ME3029, TAC ME3030, TAC ME3031, TAC ME3032, TAC ME3033, TAC ME3034, TAC ME3035, TAC ME3036, TAC ME3038, TAC ME3039, TAC ME3040, TAC ME3041, TAC ME3042, TAC ME3043, TAC ME3044, TAC ME3037 |
Download: ML100880085 (3) |
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Category:Acceptance Review Letter
MONTHYEARML23086A0822023-03-27027 March 2023 Acceptance of Requested Licensing Action for Exemption Request to Support Digital Modernization Project Installation ML22339A0642022-12-0909 December 2022 Generation Station, Unit Nos. 1 and 2 Acceptance of Requested Licensing Action Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML22320A1132022-11-21021 November 2022 Generation Station, Units 1 and 2 - Supplemental Information Needed for Acceptance of Digital Instrumentation and Controls License Amendment Requests ML22179A2912022-10-27027 October 2022 Withdrawal of Proposed Alternative to Use ASME Code Case N-921 for the Sixth Inservice Inspection Intervals ML22112A2152022-03-28028 March 2022 Limerick_Acceptance Review TS Change to Correct Nonconservative Technical Specification Table 3.3.3-1 ML22076A2362022-03-23023 March 2022 Acceptance of Requested Licensing Action Amendment to Expand the Use of Prime Methods ML21342A3402021-12-0808 December 2021 Acceptance Review: License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times ML21322A3112021-11-18018 November 2021 Acceptance Review: Quad Cities Units 1 and 2 - License Amendment Request New Fuel Vault Storage and Spent Fuel Pool Criticality Methodologies ML21294A0032021-10-26026 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding Transition to GNF3 Fuel IR 05000456/20210102021-07-19019 July 2021 Triennial Fire Protection Inspection Report 05000456/2021010 and 05000457/2021010 ML21162A1172021-06-11011 June 2021 E-mail to HDI: Acceptance Review - FOF Exemption ML21139A1722021-05-19019 May 2021 Acceptance Review Memo Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Pressure Retaining Bolting Requirements ML21140A0842021-05-19019 May 2021 Acceptance of Requested Licensing Action Revision to Appendix C License Conditions in Accordance with the Requirements of 10 CFR 50.69 (E-mail) ML21113A0742021-04-23023 April 2021 Acceptance Review Email - April 20, 2021 Oyster Creek Request for Exemption from 10 CFR Part 73 Requirements Due to Covid ML21111A0312021-04-20020 April 2021 Application to Modify 50.69 Categorization to Implement an Alternate Defense-in-Depth Categorization Process, an Alternate Pressure Boundary Categorization Process, and an Alternate Seismic Tier 1 Categorization Process ML21105A0002021-04-12012 April 2021 Acceptance Review (LAR)-Dresden Nuclear Power Station, Units 1, 2, and 3, Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently De-fueled Condition ML21103A0082021-04-12012 April 2021 Acceptance Review (Exemption Request): Dresden Nuclear Power Station, Units 1, 2, and 3-Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E ML21077A1772021-04-0808 April 2021 Withdrawal of Requested Exemption from Certain Requirement in 10 CFR 50.55a (Epids L-2021-LLE-0014, 0015, & 0016) ML21081A0222021-03-19019 March 2021 Acceptance Review for Dresden Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ML21081A0792021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ML21081A0972021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events (EPID L-2021-JLD-0004) (E-mail) ML21064A2432021-03-0505 March 2021 Email from Z. Cruz to A. Sterdis Acceptance Review_ Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Facility Only Emergency Plan and Emergency Action Level Scheme ML21011A1062021-01-12012 January 2021 Decommissioning International: Review and Acceptance of the Holtec Decommissioning International Fleet Decommisioning Quality Assurance Program ML20343A1372020-12-0707 December 2020 Acceptance Review Dresden, Units 2 and 3, LAR for Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML20343A3492020-12-0707 December 2020 Acceptance of Requested Licensing Action: Peach Bottom Relief Request for N-16 Nozzle ML20332A1472020-11-24024 November 2020 Acceptance Review: November 20 2020 Exemption Request from 10 CFR Part 73 Appendix B Requirements for Oyster Creek ML20317A3112020-10-30030 October 2020 Acceptance of Requested Licensing Action: Certified Fuel Handler Training and Retraining Program ML20304A1432020-10-30030 October 2020 Acceptance Review: Relocation of Pressure and Temperature Limit Report ML20295A5572020-10-19019 October 2020 Status of Acceptance Review for Dresden Administrative LAR Dated 9/24/2020 ML20276A0762020-10-0202 October 2020 Acceptance of Requested Licensing Action, One-Time Acceptance for Review - Peach Bottom of Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML20273A1582020-09-29029 September 2020 Acceptance Review: to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20268B2362020-09-24024 September 2020 Acceptance Review: Relief Requesting Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations ML20266G4032020-09-22022 September 2020 Acceptance Review Email - Request for Approval of HDI Fleet Decommissioning Quality Assurance Program, Revision 0 ML20092G8352020-04-0101 April 2020 Acceptance Review - TS Change 3.10.8, Inservice Leak - TSTF-484 ML20091N0492020-03-27027 March 2020 Acceptance Review: TS Change for Testing of the SRVs to Retain the Frequency and Associated Relief Requests in the IST Program (EPIDs L-2020-LLA-0052 and L-2020-LLA-0043) ML20042D4542020-02-11011 February 2020 Acceptance of Requested Licensing Action Exemption Request from 10 CFR 140.11(a)(4) Primary and Secondary Liability Insurance Requirements ML19357A0892019-12-23023 December 2019 Acceptance Review: Technical Specification 40.5 Requirements to Reflect the Allowance Provided in 10 CFR 50.69(b)(1)(v) to Perform Alternative Treatement of SSC J(Epid: L-209-LLA-263) ML19347B0312019-12-12012 December 2019 Acceptance of Requested Licensing Action Amendment Request to Remove Permanently Defueled Technical Specification 3/4.1.4 ML19340A0952019-12-0505 December 2019 Rc Acceptance Review Dresden, Units 2 and 3 - Request for Relief (RR-I5R-04, R2) ML19324F4812019-11-20020 November 2019 Increase Allowable MSIV Leakage Rates ML19322C1622019-11-18018 November 2019 Acceptance Review for Peach Bottom - ISI 4th Interval I4R-63 ML19260D1852019-09-16016 September 2019 Acceptance Review for Peach Bottom - Standby Liquid Control Nozzle 5th ISI Interval ML19248B7322019-09-0505 September 2019 Letter to R. Libra Alternative Request Pertaining to Dry Shielded Canisters Equipped with Boral Neutron Absorber Plates - Accepted for Review ML19239A1552019-08-26026 August 2019 Acceptance Review for Limerick - Relocation of Chlorine and Toxic Gas Detection System TSs License Amendment Request ML19164A1502019-06-13013 June 2019 Acceptance for Review of Application to Increase Technical Specification Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement ML19030A1472019-01-30030 January 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action to Adopt Risk-Informed Completion Times in Accordance with TSTF-505, Revision 2 ML18295A5312018-10-22022 October 2018 Acceptance Review: Relief Request I4R-08, Revision 1 for the Fourth Inservice Inspection Interval of Limerick Generating Station (LGS) Units 1 and 2 ML18295A3912018-10-22022 October 2018 Acceptance Review for Peach Bottom - License Amendment Request for Secondary Containment ML18295A2602018-10-22022 October 2018 Acceptance Review for Peach Bottom - License Amendment Request for TS Changes Related to HPSW System ML18254A2042018-09-10010 September 2018 Acceptance Review for Peach Bottom - License Amendment Request for Expanded Actions for LEFM Conditions 2023-03-27
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 21, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO.1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2, AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNITS 1 AND 2 -ACCEPTANCE REVIEW RE: IMPLEMENTATION OF EMERGENCY ACTION LEVEL SCHEMES DEVELOPED FROM NEI 99-01, REVISION 5 (TAC NOS. ME3028, ME~029, ME3030, ME3031, ME3032, ME 3033, ME3034, ME3035, ME3036, ME3037, ME3038, ME3039, ME3040, ME3041, ME3041, ME3042, ME3043, AND ME3044)
Dear Mr. Pacilio:
By letter to the Nuclear Regulatory Commission (NRC) dated December 22, 2009 (Agencywide Documents Access and Management System (ADAMS) (non-public) Accession No. ML100050503), Exelon Generation Company, LLC (the licensee). submitted a request for NRC review and approval of revisions to the Emergency Plan (EP) Emergency Action Levels (EALs) for the subject plants. The proposed EP changes would incorporate EALs based on the NRC-endorsed methodology Nuclear Energy Institute (NEI) 99-01, Revision (Rev) 5, "Methodology for Development of Emergency Action Levels," dated February 22,2008 (ADAMS Accession No. ML080450149).
By memo dated July 8, 2010 (ADAMS Accession No. ML101890434), the NRC staff concluded that an entire revision from NEI 99-01, Rev. 4 to Rev. 5 is an EAL scheme change that requires prior NRC review and approval per Appendix E to 10 CFR 50. Specifically, EAL scheme changes require approval pursuant to 10 CFR Part 50, Appendix E, Section IV(B)( 1).
In accordance with the requirements of 10 CFR Part 50, Appendix E, Section IV(B)(1), the licensee requested NRC staff review and approval to adopt EALs based on NEt 99-01, Rev 5.
The existing EAL scheme for the subject facilities is the NEI 99-01, Rev 4 methodology.
The purpose of this letter is to provide the results of the NRC staff's acceptance review of the proposed changes to the EP EALs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its
M. Pacilio -2 detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your application, and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review, and make an independent assessment regarding the acceptability of the proposed changes in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions regarding this matter, I may be reached at(301} 415-1115 or via email at nicholas.difrancesco@nrc.gov.
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Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, 50-457, 50-454, 50-455, 50-461,50-237,50-249,50-373,50-374,50-352,50-353, 50-219, 50-277, 50-278, 50-254, 50-265, 50-289, and 50-320 cc: Distribution via Listserv
ML100880085 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA NSIRIORLOB/BC CGratton for NAME NDiFrancesco THarris* JAnderson* HChemoff RCarison TE 07/21/10 07/14/10 07/13/10 07120/10 07121/10