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MONTHYEARBSEP 17-0033, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay2017-04-0606 April 2017 Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay Project stage: Request BSEP 17-0036, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-04-12012 April 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 Project stage: Other BSEP 17-0042, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-04-24024 April 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 Project stage: Other ML17096A3332017-05-0909 May 2017 Verbal Authorization of Relief Request for Reactor Vessel Closure Head Penetration Nozzle N9 Repair Project stage: Other BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-07-10010 July 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 Project stage: Other ML17230A2742017-10-10010 October 2017 Relief from the Requirements of the ASME Code, Section XI, IWA-4000 (Inservice Inspection Program Alternative ISI-07) Project stage: Approval BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination Project stage: Request ML17355A0102017-12-20020 December 2017 NRR E-mail Capture - Brunswick Steam Electric Plant, Unit 2, Acceptance Review for Proposed Alternative ISI-08 for Reactor Vessel Nozzle-to-Vessel Weld Examination Project stage: Acceptance Review BSEP 18-0026, Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2018-03-0707 March 2018 Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination Project stage: Request ML18117A1912018-05-0404 May 2018 Proposed Alternative to Defer Inspection of Reactor Vessel Instrumentation Nozzle 2B11-RPV-N11B Until the First Period in the 5th 10-Year ISI Interval Project stage: Other 2017-04-24
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Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner 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 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 ML21343A2002021-12-20020 December 2021 Authorization and Safety Evaluation for Alternative from Certain Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code of Buried Service Water Piping (EPID L-2021-LLR-0014) (Non-Proprieta ML21305B8292021-11-23023 November 2021 Approval of Exemption from 10 CFR 55.47 - Waiver of Examination and Test Requirements 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 RA-20-0045, RA-20-0045, Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior2020-03-31031 March 2020 RA-20-0045, Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior ML18124A3052018-05-0909 May 2018 Alternative for ISI-09 Regarding Reactor Pressure Vessel Shell Welds Fourth Ten-Year Inservice Inspection Interval BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test2018-03-23023 March 2018 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination ML17230A2742017-10-10010 October 2017 Relief from the Requirements of the ASME Code, Section XI, IWA-4000 (Inservice Inspection Program Alternative ISI-07) ML17096A3332017-05-0909 May 2017 Verbal Authorization of Relief Request for Reactor Vessel Closure Head Penetration Nozzle N9 Repair ML16343A9432017-02-27027 February 2017 Relief from the Requirements of the ASME Code Section XI Inservice Inspection Requirements (Relief Request ISL-06) ML17038A5522017-02-16016 February 2017 Relief from the Requirements of the ASME Engineers Code for Operation and Maintenance for Inservice Testing Requirements (Relief Request VRR-06) ML1009605472010-04-30030 April 2010 Relief Requests RR-42, RR-43, RR-44, RR-45, for the Third 10-Year Interval Inservice Inspection Program Plan ML1004912692010-04-0707 April 2010 Relief Request (RR) Number RR-46 for the Third 10 Year Inservice Inspection Interval (TAC Nos. ME1249 and ME1250) ML0827607522008-11-19019 November 2008 Fourth 10-Year Interval Inservice Inspection Request Relief PT-02 for Proposed Alternative Inspection for Standby Gas Treatment System ML0826000752008-11-0404 November 2008 Relief Request ISI-02 Regarding the Continued Use of the Risk-Informed Inservice Inspection Program ML0703604182007-02-12012 February 2007 Request for Relief No. RR-38 Regarding Pressure Testing of Drain, Vent, Test, and Fill Lines within the Reactor Coolant Pressure Boundary ML0608902032006-04-27027 April 2006 Request for Relief Request No. VRR-15 for Regarding Check Valves Related to the Third 10-Year Inservice Testing Program ML0605200512006-02-23023 February 2006 Request for Relief No. 37. Revision 1, Regarding the Duties of the Authorized Nuclear Inservice Inspector BSEP 05-0063, Relief Request VRR-15, Emergency Diesel Generator Service Water Check Valves2005-05-26026 May 2005 Relief Request VRR-15, Emergency Diesel Generator Service Water Check Valves ML0509701312005-04-21021 April 2005 Relief Request, Usage of Recent ISI Testing Requirements for Pressure Relief Device Testing ML0506801572005-04-0101 April 2005 Relief Request, Use of Recent Inservice Testing Requirements ML0505300212005-03-0707 March 2005 RR-34, CRD System Hydraulic Lines Structural Integrity (Tac No. MC5037 and MC5038) BSEP 03-0069, Withdrawal of Inservice Inspection Program Relief Request for Service Water System Piping Non-Code Repair2003-05-12012 May 2003 Withdrawal of Inservice Inspection Program Relief Request for Service Water System Piping Non-Code Repair ML0308605252003-03-26026 March 2003 Request for Relief from Third 10-Year Interval Inservice Inspection Program Plan Request for Relief RR-31 ML0307000212003-03-21021 March 2003 Relief ,Third 10-Year Interval Inservice Inspection Program Plan Relief RR-29 and RR-30 for Brunswick Units 1 & 2 BSEP 02-0175, Inservice Inspection Program Relief Request - Service Water System Piping Through-Wall Flaw2002-10-25025 October 2002 Inservice Inspection Program Relief Request - Service Water System Piping Through-Wall Flaw 2023-09-25
[Table view] Category:Memoranda
MONTHYEARML23151A2532023-05-31031 May 2023 Meeting Summary of 2022 Annual Assessment Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324, Meeting Number 20230392 ML22130A0302022-05-0909 May 2022 Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350 ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21131A1472021-05-11011 May 2021 Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385 ML20136A2222020-05-15015 May 2020 Har - Bru 2019 Aam Meeting Summary ML19254B4692019-09-0909 September 2019 (FEMA Letter NRC 09-09-19) Preliminary Capabilities Assessment - Brunswick Nuclear Power Plant ML19266A5332019-09-0909 September 2019 (FEMA Memo to NRC 9-9-19) Preliminary Capabilities Assessment - Brunswick Nuclear Plant ML19123A3532019-05-0202 May 2019 Public Meeting Summary - Brunswick Steam Electric Plant, Docket Nos. 05000325 and 05000324 ML18116A1082018-04-26026 April 2018 Summary of Meeting on Annual Assessment Public Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 05000325 and 05000324 ML17137A3332017-05-17017 May 2017 Meeting Summary Regarding 2016 Annual Assessment of the Brunswick Steam Electric Plant for Period of January 01, 2016 Through December 31, 2016 ML17129A3022017-05-17017 May 2017 Office of Nuclear Security and Incident Response Observation of 2017 Security Baseline Inspection at Brunswick Steam Electric Plant, Units 1 & 2 ML17096A3332017-05-0909 May 2017 Verbal Authorization of Relief Request for Reactor Vessel Closure Head Penetration Nozzle N9 Repair ML16286A2372016-10-12012 October 2016 FEMA Assessment of Offsite Plans and Preparedness Post-Hurricane Matthew (October 2016) ML16134A1742016-05-12012 May 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Brunswick, Units 1 and 2 ML16034A5082016-02-0404 February 2016 Audit Report; Brunswick Steam Electric Plant, Units 1 & 2 Nuclear Facility Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1 (TAC No. MF5852) ML15303A3962015-12-0808 December 2015 Safety Evaluation Input on Emergency Action Level Scheme Upgrade for Brunswick Steam Electric Plant Units 1 and 2 (TAC No'S. MF5766 and MF5767 ML15125A4602015-05-0505 May 2015 Summary of Public Meeting to Discuss the Annual Assessment of the Brunswick Steam Electric Plant with the Public for the Period of January 1, 2014, Through December 31, 2014 ML14140A1882014-05-19019 May 2014 Summary of Public Meeting - 2013 Annual Assessment Regrading Brunswick Steam Electric Plant ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13295A3062013-10-22022 October 2013 Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC ML13221A5122013-08-12012 August 2013 8/20/2013 - Closed Notice of Forthcoming Meeting with Duke Energy Regarding Mella Brunswick Steam Electric Plant, Units 1 and 2 ML13106A3372013-04-17017 April 2013 Notice of Forthcoming Meeting with Duke Energy, Inc. Concerning the Relocation of the Emergency Operating Facilities ML12346A2842012-12-18018 December 2012 Forthcoming Public Conference Call Meeting with Duke Energy Carolinas Re Mellla+ for Brunswick Steam Electric Plant, Units 1 and 2, to Discuss the Maximum Extended Load Limit Analysis Plus (Mellla+) Implementation ML12177A4302012-11-0909 November 2012 Task Interface Agreement (Concurrence)-Operability of Brunswick, Unit 2, Reactor Water Cleanup System Isolation Instrumentation with the Inlet Flow Orifice Installed Backwards (TIA 2012-09) ML12300A4032012-10-26026 October 2012 11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events ML12284A4612012-10-12012 October 2012 Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events ML12160A5732012-06-11011 June 2012 Meeting Notice - Forthcoming Pre-Application Conference Call with Carolina Power and Light Company Regarding National Fire Protection Association Standard 805 for Brunswick Steam Electric Plant, Units 1 and 2 ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML12144A2802012-05-23023 May 2012 Notice of Forthcoming Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2 ML12128A3462012-05-10010 May 2012 Meeting Notice - Forthcoming Notice of Pre-application Meeting with Carolina Power & Light Company Regarding NFPA805 ML1132504952011-11-21021 November 2011 Special Inspection Charter to Evaluate Brunswick Reactor Vessel Head Tensioning Issue ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1108406312011-03-29029 March 2011 Notice of Forthcoming Pre-Application Meeting with Carolina Power & Light Co. and Florida Power Corp., Brunswick Units 1 & 2, Crystal River Unit 3, and H.B. Robinson Unit 2, to Discuss Transition to the Requirements of National Fire.. ML1028504852010-10-0707 October 2010 S. Wastler Memo Technical Assistance Request - Review of Proposed Amendment to the Brunswick Steam Electric Station Plant Physical Security Plan (TAC L24477) ML1015901992010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of Progress Energy Carolina'S Ownership Interest of H.B. Robinson Steam Electric Plant Unit 2, Brunswick Steam Electric Plant Units 1 and 2 & Shearon Harris Nuclear Power Plant Unit ML1015900142010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 20, 2010 - Finding of No Potential Issues in Bank ML1015805092010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 21, 2010 - Finding of No Potential Issues in Bank ML0815606912008-07-11011 July 2008 Transmittal of Final Accident Sequence Precursor (ASP) Analyses of Operational Events That Occurred at D.C. Cook, Unit 2 on November 8, 2005 and at Brunswick, Unit 2 on November 1, 2006 ML0812802272008-05-0202 May 2008 Memorandum from Hubert T. Bell to Chairman Dale E. Klein, NRC Staff Review of License Renewal Applications ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0733711662007-12-0303 December 2007 Notice of Meeting with Progress Energy & Duke Energy Regarding Fire Probabilistic Risk Assessment for the Pilot Plants Transitioning to the National Fire Protection Association Standard NFPA 805 ML0717601722007-06-25025 June 2007 Summary of Closed Meeting with Progress Energy to Discuss Security Threat-Based Event Emergency Preparedness (EP) Drill at the Brunswick Steam Electric Plant ML0715503752007-06-0404 June 2007 Notice of Meeting with Brunswick Steam Electric Plant Regarding Security-Based Event Emergency Preparedness Drill Scenario Review ML0614505922006-05-26026 May 2006 Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report ML0613601312006-05-12012 May 2006 Cost-Beneficial Severe Accident Mitigation Alternatives (Samas) Identified During the License Renewal Review for the Brunswick Steam Electric Plant, Units 1 and 2 ML0601003992006-01-0404 January 2006 1/4/06 - Trip Report - November 29, 2005, Essential Fish Habitat Meeting and Tour ML0526503162005-09-23023 September 2005 Notice of Category 1 Meeting with Carolina Power and Light Co., Brunswick Units 1 and 2 MSIV TS Revisions ML0515803862005-06-0707 June 2005 Ltr, Request for Emergency Publication ML0232903632004-09-29029 September 2004 RAI Data for Incorporation Into Power Uprate Review Standard 2023-05-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 9, 2017 MEMORANDUM TO: Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation l ./ j' FROM: Andrew Hon, Project Manager __ -:fa 4' .___ { -----*---
Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 - VERBAL AUTHORIZATION OF RELIEF REQUEST FOR REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLE N9 REPAIR (CAC NO. MF9561)
By letter dated April 6, 2017 (ADAMS Accession No. ML17096A619), Duke Energy Progress, LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, at the Brunswick Steam Electric Plant Unit No. 2. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(1), the licensee submitted lnservice Inspection (ISi) Program Alternative ISl-07 for the alternate repair of the degraded dissimilar metal butt weld, B211 N9-RPV-FW2CRD52, of the control rod drive return line nozzle N9, on the basis that the alternate repair provides an acceptable level of quality and safety.
The NRC staff finds that the proposed weld overlay will be designed, installed, and inspected consistent with Code Cases N-504-4 and N-638-4, and ASME Code,Section XI, Appendices VIII and Q. Therefore, the NRC finds that the proposed alternative will provide reasonable assurance that the structural integrity of the subject component is acceptable for the life of the plant. During a conference call with the licensee on April 6, 2017, the NRC staff granted a verbal authorization on the use of ISi Program Alternative ISl-07 in accordance with 10 CFR 50.55a(z)(1 ). The script for the verbal authorization is enclosed.
NRC
Participants:
Licensee
Participants:
B. Beasley D.Alley L. Grzeck D. Goins A. Hon J. Tsao M. Classe J. Nolin M. Catts W. Murray Docket No. 50-324
Enclosure:
Verbal Authorization Script
VERBAL AUTHORIZATION BY THE OFFICE NUCLEAR REGULATION FOR INSERVICE INSPECTION PROGRAM ALTERNATIVE ISl-07 ALTERNATE REPAIR OF CONTROL ROD DRIVE RETURN LINE NOZZLE N9 BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 2 DUKE ENERGY PROGRESS DOCKET NO. 50-324 APRIL 6, 2017 Technical Evaluation read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, Office of Nuclear Reactor Regulation By letter dated April 6, 2017, Duke Energy Progress (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, at the Brunswick Steam Electric Plant Unit No. 2.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1 ), the licensee submitted lnservice Inspection Program Alternative ISl-07 for the alternate repair of the degraded dissimilar metal butt weld, B211 N9-RPV-FW2CRD52, of the control rod drive return line nozzle N9 on the basis that the alternate repair provides an acceptable level of quality and safety.
The licensee detected a circumferential indication located within the subject weld and butter.
The estimated length of the indication is 6.36 inches. The depth of the indication is 0.323 inches with a remaining ligament from the outside weld surface of 0.544 inches. The indication is located 5.50 inches clockwise from top dead center (looking at the nozzle).
The licensee proposed to install a weld overlay on the subject weld using ASME Code Case N-740-2, "Dissimilar Metal Weld Overlay for Repair or Mitigation of Class 1, 2, and 3 Items."
The NRC staff has not approved Code Case N-740-2. To evaluate the proposed alternative, the NRC staff used NRC-approved ASME Code Case N-504-4 "Alternative Rules for Repair of Classes 1, 2 and 3 Austenitic Stainless Steel Piping," Code Case N-638-4, "Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW [gas tungsten arc welding] Temper Bead Technique, and ASME Code,Section XI, Appendices VIII and Q.
The NRC staff finds that the proposed weld overlay is designed, installed, and inspected consistent with Code Cases N-504-4 and N-638-4, and ASME Code,Section XI, Appendices VIII and Q. Therefore, the NRC finds that the proposed alternative will provide reasonable assurance that the structural integrity of the subject component is acceptable for the life of the plant.
Enclosure
Authorization read by Benjamin G. Beasley, Chief of the Plant Licensing Branch 11-2, Office of Nuclear Reactor Regulation As Chief of the Plant Licensing Branch 11-2 in the Office of Nuclear Reactor Regulation, I concur with the conclusions of the Component Performance, Non-Destructive Examination, and Testing Branch.
The NRC staff concludes that the proposed alternative provides reasonable assurance of structural integrity of the subject dissimilar metal butt weld of the control rod drive return line nozzle N9. As such, the NRC staff finds that the alternate repair provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, as of April 6, 2017, the NRC authorizes the use of lnservice Inspection Program Alternative ISl-07 at Brunswick Steam Electric Plant Unit No. 2 for the fourth 10-Year ISi interval which ends on May 10, 2018. The NRC staff concludes that weld overlay provides acceptable structural integrity and may remain in place for the remaining life of the plant.
All other requirements in ASME Code,Section XI, for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding the proposed alternative while preparing subsequent written safety evaluation.
ML17096A333 OFFICE N RR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DE/EPNB/BC NAME AHon ( MWentzel for) BClayton DAiiey DATE 05/02/2017 05/01/2017 05/02/2017 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BBeasley A Hon DATE 05/09/2017 05/09/2017