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MONTHYEARNL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...2018-07-27027 July 2018 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ... Project stage: Request ML18243A4062018-08-31031 August 2018 Acceptance of Licensing Action Regarding Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b Project stage: Acceptance Review ML18290B0942018-10-16016 October 2018 October 16, 2018, Public Meeting Presentation Slides Related to July 27, 2018, License Amendment Request to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b. Project stage: Meeting ML18306A3132018-11-0707 November 2018 Summary of October 16, 2018, Meeting with Southern Nuclear Operating Company, Inc., to Discuss the Joseph M. Farley Unit 1 & 2, Electrical Distribution System as It Relates to the Risk-Informed Completion Times Amendment Project stage: Meeting ML18338A0052019-01-0404 January 2019 Regulatory Audit in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B Project stage: Acceptance Review ML19042A1082019-02-26026 February 2019 Audit Summary in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B Project stage: Other ML19072A0272019-03-12012 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4B Project stage: Acceptance Review NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) Project stage: Response to RAI NL-19-0623, Significant Hazards Evaluation and Environmental Considerations for Farley Risk Informed Technical Specifications Response to Request for Additional Information2019-05-17017 May 2019 Significant Hazards Evaluation and Environmental Considerations for Farley Risk Informed Technical Specifications Response to Request for Additional Information Project stage: Response to RAI NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes Project stage: Request ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A Project stage: Approval NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission Project stage: Request ML22060A1892022-03-15015 March 2022 Correction to TS Pg 3.6.6-4 During Issuance of Amendment Nos. 225 and 222 Project stage: Approval 2019-03-12
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Category:Audit Report
MONTHYEARML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions ML21260A1612021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML20115E4532020-05-0101 May 2020 Audit Summary in Support of the License Amendment Request Technical Specification (TS) 3.3.7 ML19042A1082019-02-26026 February 2019 Audit Summary in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B ML16014A7342016-02-0808 February 2016 Report for the Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 ML13337A5842014-01-17017 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML0832900802008-12-0505 December 2008 Audit of Licensee'S Management of Regulatory Commitments ML0515700752005-06-0909 June 2005 Audit of the Licensee'S Management of Regulatory Commitments ML0425402772004-09-10010 September 2004 Audit and Review Report for Plant Aging Management Reviews and Programs for the Joseph M. Farley Nuclear Plant, Units 1 and 2. 2024-08-22
[Table view] Category:Letter
MONTHYEARIR 05000348/20244032024-11-13013 November 2024 – Security Baseline Inspection Report 05000348/2024403 & 05000364/2024403 IR 05000348/20240032024-11-13013 November 2024 Integrated Inspection Report 05000348/2024003, 05000364/2024003 and 07200042/2024001 NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 2024-09-05
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Text
Ms. Cheryl A. Gayheart Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2019 Southern Nuclear Operating Company, Inc. 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -AUDIT
SUMMARY
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 48 (EPID L-2018-LLA-0210)
Dear Ms. Gayheart:
By letter dated July 27, 2018, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019. The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information.
The audit summary report is provided as an enclosure to this letter.
C. Gayheart If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Docket Nos. 50-348 and 50-364
Enclosure:
- 1. Audit Summary cc: Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FEBRUARY 5-7, 2019, AUDIT
SUMMARY
LICENSE AMENDMENT REQUEST TO ADOPT NEI 06-09, REVISION 0-A RISK-INFORMED COMPLETION TIMES SOUTHERN NUCLEAR OPERA TING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated July 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18208A619), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute (NEI) 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019 (ADAMS Accession No. ML 18338A005) that included 26 questions to be discussed during the audit. The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information (RAls). The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195).
2.0 AUDIT ACTIVITIES AND OBSERVATIONS The purpose of the audit was to understand the calculations, analyses, and bases for the LAR, and to develop requests for additional information, as needed. NRC staff discussions with SNC focused on internal events and fire probabilistic risk assessment (PRA) quality, PRA functionality, implementation of the risk informed completion time (RICT) program, TS limiting conditions for operation, and associated RICT program guidance documents.
SNC provided a demonstration of how it would implement the RICT. The NRC staff reviewed applicable program documents.
The following are the specific presentation and discussion topics discussed during the audit:
- SNC Presentation of Electrical Systems Modeled in the PRA (Question
- 25)
- Configuration Risk Management Program (CRMP) Tool Overview Enclosure
- SNC Presentation of Responses to Questions 12, 19, 20, 21 and 24 (LAR/TS)
- Loss of Function Discussion and SNC response to Questions 13, 15, 16, and 18
- External Hazards Discussion and SNC response to Question 11
- SNC Presentation of PRA Functional Definition, Development and Use
- SNC responses to Questions 14, 17, 22, and 23 (PRA Functionality)
- Presentation of Risk Management Actions (RMAs) Determinations
/Examples (plus SNC response to 026)
- Detailed CRMP Presentation
- PRA Quality Discussion and SNC responses to Questions 1, 2, 3, 6, 8, 10
- SNC responses to Questions 4 and 5 (PRA Modeling)
- SNC responses to Questions 7 and 9 (Uncertainties)
Audit Exit: NRC staff went through each question/discussion topic in the Audit plan, and shared preliminary thoughts on any changes to the original set of questions/discussion topics. There were no regulatory decisions made regarding the final set of questions.
NRC staff stated that they planned to issue a formal RAI within 30 days of the Audit. 4.0 AUDIT PARTICIPANTS NRC Participants:
- Shawn Williams, Project Manager, Office of Nuclear Reactor Regulation (NRR), Division of Reactor Licensing (DORL)
- Candace De Messieres, NRR, APLA
- Gurcharan Matharu, NRR, Division of Engineering (DE), Electrical Engineering Operating Reactors Branch (EEOB)
- Victor Cusumano, NRR, Division of Safety Systems (DSS), Branch Chief Technical Specifications Branch (STSB)
- Garill Coles, PNNL (Contractor)
SNC Participants:
- Matthew Warden 5.0 DOCUMENTS REVIEWED The following documents were available on the Farley Portal, and reviewed by NRC and PNNL staff. 1. SNC Calculation PRA-BC-F-17-002, "Seismic Risk Evaluation based on IPEEE and EPRI 2014 Farley Seismic Hazard," Version 1 (Reference 6 of Enclosure 4 to NL-18-0039), and 2. "Joseph M. Farley Nuclear Plant Units 1 and 2, Evaluation of Other External Hazards," Southern Nuclear PRA Report, Revision 0, December 31, 2013 (Reference A.2-2 of Enclosure 3 to NL-18-0039).
- 3. Draft Responses to the Audit Questions.
- 4. F-RIE-FIREPRA-U00-014, Fire PRA Quantification and Summary Report, Revision 1 5. F-RIE-IEIF-U00-01, Internal Events and Internal Flooding and LERF Model Update" Revision 10, Version 2.0. 6. F-RIE-IEIF-U00-013, Characterizing the Sources of Model Uncertainty for Farley Nuclear Plant 7. 05058-RPT-011, Farley Fire PRA Uncertainty Analysis, Revision 2 8. NMP-GM-031-003, Risk Management Actions for RICT Program, Version 4.0 9. NMP-GM-031-002, Calculation of RMAT and RICT for the RICT Program, Version 3.1 10. NMP-GM-031-004, PRA Functionality Determination
- 11. FNP-O-SOP-0.13, Recording Limiting Conditions for Operation
- 12. SNCF-00358-REPT-001, Farley Internal Events F&O Closure Review (ENERCON)
- 13. F-FIE-FIREPAR U00-014, Internal Events PRA Uncertainty Analysis 14. FNP-O-AOP-21.0, Severe Weather Abnormal Operating Procedure
- 15. SNCF-00355-REPT-001, Farley Fire PRA Focused-Scope Peer Review, July 2018 (ENERCON)
- 16. R-401292913-255, Farley Fire PRA Focused-Scope Peer Review, January 2018 (ABS Consulting)
C.Gayheart
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -AUDIT
SUMMARY
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 4B (EPID L-2018-LLA-0210)
DATED FEBRUARY 26, 2019 DISTRIBUTION:
PUBLIC RidsACRS MailCTR Resource RidsNrrLAKGoldstein Resource RidsNrrPMFarley Resource RidsRgn2MailCenter Resource MBiro, NRR VCusumano, NRRs BTjader, NRR GMatharu, NRR CDeMessieres, NRR JEvans, NRR DWu, NRR SVasavada, NRR ADAMS Accession No. ML 19042A108 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1
/LA NRR/DE/APLA/BC*
NAME SWilliams KGoldstein MWentzel DATE 02/22/19 02/14/19 02/22/19 OFFICE NRR/DORL/LPL2-1
/PM NAME SWilliams DATE 02/26/19 OFFICIAL RECORD COPY *via E-mail NRR/DORL/LPL2-1/BC MMarkley 02/26/19