Letter Sequence Other |
---|
|
|
MONTHYEARML1013700652010-05-14014 May 2010 Part 21 Reportable Condition Notification: Bent Fuel Spacer Flow Wing - GNF2 Fuel Project stage: Request ML1035001802010-12-15015 December 2010 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change Project stage: Request ML1100600092011-01-0606 January 2011 Acceptance Review of Limerick Unit 2 Safety Limit Minimum Critical Power Ratio License Amendment Request Project stage: Acceptance Review ML1100605942011-01-18018 January 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML1103304292011-02-0303 February 2011 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes Project stage: Draft RAI ML1103401732011-02-0404 February 2011 Request for Additional Information Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes Project stage: RAI ML1104905722011-02-17017 February 2011 Response to Request for Additional Information Concerning the Safety Limit Minimum Critical Power Ratio Change License Amendment Request Project stage: Response to RAI ML1106103602011-03-0404 March 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML1107701842011-03-17017 March 2011 Response to Request for Additional Information Concerning the Safety Limit Minimum Critical Power Ratio Change License Amendment Request Project stage: Response to RAI ML1108109282011-03-25025 March 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML1107504462011-04-0505 April 2011 License Amendment, Safety Limit Minimum Critical Power Ration Changes Project stage: Other ML1110403432011-09-15015 September 2011 Correction Letter for Limerick Generating Station, Unit 2 - Safety Evaluation Regarding Safety Limit Minimum Critical Power Ratios Project stage: Approval 2011-02-03
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval ML23325A2062023-11-21021 November 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23313A0432023-11-13013 November 2023 Summary of Regulatory Audit in Support of Amendment Request for Control Room Air Conditioning Technical Specifications ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000352/20230032023-10-27027 October 2023 Integrated Inspection Report 05000352/2023003 and 05000353/2023003 and Independent Spent Fuel Storage Installation Inspection 07200065/2023001 ML23297A1722023-10-24024 October 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000352/2024010 and 05000353/2024010 IR 05000352/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000352/2023501 and 05000353/2023501 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23276A5162023-10-0303 October 2023 Federal Emergency Management Agency Level 1 Finding from 2023 Evaluated Emergency Preparedness Exercise ML23275A1082023-09-29029 September 2023 FEMA Level 1 Findings Limerick NPP- Boyertown/Colebrookdale ML23241A9452023-09-27027 September 2023 Generation Station, Units 1 and 2 Regulatory Audit Plan Supporting Review of the Equipment Qualification Portion of Limerick Digital Instrumentation and Controls License Amendment Request ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23255A0952023-09-12012 September 2023 Resubmittal of License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) to Address ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A1002023-09-0606 September 2023 Requalification Program Inspection IR 05000352/20230052023-08-31031 August 2023 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2023005 and 05000353/2023005) ML23248A2082023-08-31031 August 2023 UFSAR Cover Page ML23242A2172023-08-30030 August 2023 Response to Request for Additional Information for Application to Adopt TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems and Associated Technical Specification Changes NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23228A0942023-08-16016 August 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . IR 05000352/20230022023-08-14014 August 2023 Integrated Inspection Report 05000352/2023002 and 05000353/2023002 ML23220A0182023-08-0808 August 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000352/2023401 and 05000353/2023401 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212B2362023-07-31031 July 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System - WEC Documents ML23212B1052023-07-31031 July 2023 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation - Revise ML23202A2192023-07-21021 July 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . ML23193B0122023-07-20020 July 2023 Audit Plan in Support of Review of License Amendment Request and Exemption Request for Digital Instrumentation and Controls Installation Support (Epids L-2023-LLA-0025 and L-2023-LLE-0005) ML23187A0962023-07-19019 July 2023 Generation Station, Unit Nos. 1 and 2 - Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23208A1522023-07-0606 July 2023 PEMA Letter Dated 7-6-23 Re Limerick Exercise 9-26-23 ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 ML23089A1242023-05-17017 May 2023 Issuance of Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization and Treatment of Structures, Systems a Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML22348A1762023-03-0707 March 2023 Issuance of Amendment Nos. 260 and 222 Regarding Technical Specifications 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML22272A0372023-01-0303 January 2023 Issuance of Amendment Nos. 258 and 220 Regarding Technical Specifications 3/4.8.1, AC Sources-Operating and 3/4.5.1, ECCS-Operating ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22003A1862022-02-17017 February 2022 Issuance of Amendment Nos. 256 and 218 Technical Specification Changes Related to Technical Specifications Task Force (TSTF) Traveler 205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21263A2482021-10-0101 October 2021 Audit Plan Supporting LAR Request to Implement Alternate Defense-in-Depth, Pressure Boundary, & Seismic Tier 1 Categorization Process in Accordance with Requirements of 10 CFR 50.69 ML21181A0442021-09-28028 September 2021 Issuance of Amendment Nos. 253 and 215 Technical Specification Changes Related to Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML21032A2702021-02-22022 February 2021 Issuance of Amendment Nos. 252 and 214, Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20255A0632020-12-0101 December 2020 Issuance of Amendment Nos. 250 and 212 Technical Specification Changes Related to Inservice Testing Program of the Safety Relief Valves ML20239A7252020-11-30030 November 2020 Issuance of Amendment Nos. 249 and 211 Adopt TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML20160A4592020-08-0707 August 2020 Issuance of Amendment Nos. 248 and 210 Revise Technical Specifications to Support Implementation of 10 CFR 50.69 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20098C9222020-04-0909 April 2020 Issuance of Amendment No. 245 Regarding Technical Specifications Change to Allow a One-Time Increase in Main Steam Isolation Valve Allowable Leakage Rate (EPID L-2020-LLA-0064) (Emergency Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML20034F6372020-02-28028 February 2020 Issuance of Amendment Nos. 240 and 203 to Implement TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19207A0062019-10-0303 October 2019 Issuance of Amendment Nos. 237 and 200 Revise Technical Specifications to Allow Penetration Flow Path Isolation for Inoperable Isolation Actuation Instrumentation ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19036A9132019-02-28028 February 2019 Issuance of Amendment Nos. 234 and 197 Adopt TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18255A2782018-11-27027 November 2018 Issuance of Amendment Nos. 232 and 195 to Revise Technical Specifications to Lower the Minimum Standby Liquid Control System Pump Flowrate ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18165A1622018-07-31031 July 2018 Issuance of Amendment Nos. 230 and 193 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components (CAC Nos. MF9873 and MF9874; EPID L-2017-LLA-0275) ML18113A0452018-05-29029 May 2018 Issuance of Amendments to Revise Technical Specification Requirements for Secondary Containment ML18025B7692018-02-28028 February 2018 Issuance of Amendment Nos. 228 and 191 Revising Technical Specifications to Relocate Main Condenser Offgas Monitoring Instrumentation and Gaseous Effluents TSs (CAC Nos. MF9650 and MF9651; EPID L-2017-LLA-0214) ML18017A2012018-02-27027 February 2018 Issuance of Amendment Nos. 227 and 190 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC Nos. MF9967 and MF9968; EPID L-2017-LLA-0260) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML17103A0812017-05-16016 May 2017 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545 ML17024A0892017-03-29029 March 2017 Issuance of Amendments Safety Limit Minimum Critical Power Ratio Change ML17047A3532017-03-15015 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16356A2722017-02-28028 February 2017 Issuance of Amendments to Revise High Pressure Coolant Injection System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications ML16335A0382016-12-29029 December 2016 Issuance of Amendments to Revise Technical Specification Snubber Requirements ML16307A0122016-12-0505 December 2016 Correction to Amendment No. 185 Regarding Application of an Alternative Source Methodology ML16041A0212016-03-15015 March 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15356A1402016-01-28028 January 2016 Issuance of Amendments Secondary Containment Access Openings ML15218A5012015-09-15015 September 2015 Issuance of Amendment Nos. 219 and 181 Proposed Change to Add New Limiting Conditions for Operation 3.0.5 and 3.0.6 ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) 2023-06-23
[Table view] Category:Safety Evaluation
MONTHYEARML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23089A1242023-05-17017 May 2023 Issuance of Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization and Treatment of Structures, Systems a Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML23094A1792023-05-17017 May 2023 Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization & Treatment of Structures, Systems, Components for NPR & Denial of Proposed Alternative Defense in Depth & Pressure Boundary Component-Partial Denial SE Encl 4 ML23094A1712023-05-17017 May 2023 Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization & Treatment of Structures, Systems and Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22348A1762023-03-0707 March 2023 Issuance of Amendment Nos. 260 and 222 Regarding Technical Specifications 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML23005A0082023-02-23023 February 2023 Technical Specifications to Correct Non-conservative Technical Specification Table 3.3.2-1 for Main Steam Line Isolation Trip Function 1.G (EPID L 2020 Lla 0034) Amds. 259 and 221 ML22272A0372023-01-0303 January 2023 Issuance of Amendment Nos. 258 and 220 Regarding Technical Specifications 3/4.8.1, AC Sources-Operating and 3/4.5.1, ECCS-Operating ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22003A1862022-02-17017 February 2022 Issuance of Amendment Nos. 256 and 218 Technical Specification Changes Related to Technical Specifications Task Force (TSTF) Traveler 205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21181A0442021-09-28028 September 2021 Issuance of Amendment Nos. 253 and 215 Technical Specification Changes Related to Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21172A2682021-09-0202 September 2021 Issuance of Relief Request I4r-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations for the Remainder of the Fourth 10-Year Isi Interval and Up to the End of the 60-Year Operating License ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21032A2702021-02-22022 February 2021 Issuance of Amendment Nos. 252 and 214, Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20322A0092020-12-10010 December 2020 Issuance of Alternative Requests 41-VRR-8 and 41-VRR-7 Regarding Certain Inservice Testing Program Requirements for Safety Relief Valves ML20255A0632020-12-0101 December 2020 Issuance of Amendment Nos. 250 and 212 Technical Specification Changes Related to Inservice Testing Program of the Safety Relief Valves ML20239A7252020-11-30030 November 2020 Issuance of Amendment Nos. 249 and 211 Adopt TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20280A7572020-11-0505 November 2020 Revised Safety Evaluation of Relief Requests GVRR-8, 11 PRR-1, 90 PRR-1, and 47 VRR-2 Regarding the Fourth 10-Year Interval of the Inservice Testing Program (EPID L-2018-LLR-0384 Through EPID L-2018-LLR-0387) ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20160A4592020-08-0707 August 2020 Issuance of Amendment Nos. 248 and 210 Revise Technical Specifications to Support Implementation of 10 CFR 50.69 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20090B4102020-06-0202 June 2020 Issuance of Relief Request GVRR-9 Associated with Pandemic-Related Issues - Inservice Testing Interval Extension for Motor Operated Valves (EPID L-2020-LLR-0046 (COVID-19)) ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20089A0012020-04-20020 April 2020 Issuance of Relief Request I4R-23 Associated with Pandemic-Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) (EPID L-2020-LLR-0044 (COVID-19)) ML20098C9222020-04-0909 April 2020 Issuance of Amendment No. 245 Regarding Technical Specifications Change to Allow a One-Time Increase in Main Steam Isolation Valve Allowable Leakage Rate (EPID L-2020-LLA-0064) (Emergency Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034F6372020-02-28028 February 2020 Issuance of Amendment Nos. 240 and 203 to Implement TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19207A0062019-10-0303 October 2019 Issuance of Amendment Nos. 237 and 200 Revise Technical Specifications to Allow Penetration Flow Path Isolation for Inoperable Isolation Actuation Instrumentation ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19099A2632019-04-22022 April 2019 Issuance of Relief Request 14R-08, Revision 1, Regarding Pressure Testing of Containment Atmospheric Control Penetration Piping ML19099A3072019-04-16016 April 2019 Issuance of Relief Request 14R-18 Associated with Inaccessible Supports for the Fourth 10-Year Inservice Inspection Interval Pipping ML19009A0022019-03-0505 March 2019 Issuance of Relief Request IR4-17, Revision 1, Reactor Pressure Vessel Nozzle Repair in Lieu of Specific ASME Code Requirements 2023-05-17
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 5, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNIT 2 -ISSUANCE OF AMENDMENT RE: SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO.
ME5182)
Dear Mr. Pacilio:
The Commission has issued the enclosed Amendment No. 162to Facility Operating License No.
NPF-85, for Limerick Generating Station (LGS), Unit 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 15, 2010 (Agencywide Documents Access and Management System Accession No. ML103500183),
supplemented by letters dated February 17, 2011 (ADAMS Accession No. ML110490572), and March 17,2011 (ADAMS Accession No. ML110770184).
The amendment consists of revisions to the TSs relating to the Safety Limit Minimum Critical Power Ratios (SLMCPRs). The changes result from a cycle specific analysis performed to support the operation of Limerick Generating Station, Unit 2, in the upcoming Cycle 12.
Specifically, the proposed TS changes will revise the SLMCPRs contained in TS 2.1.2 for two recirculation loop operation and single recirculation loop operation to reflect the changes in the cycle specific analysis.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-353
Enclosures:
- 1. Amendment No.162 to License No. NPF-85
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. NPF-85
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee), December 15, 2010, as supplemented by letters dated February 17, 2011, and March 17, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
- 2 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 162, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
/l~;t::7SSION Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: Apr; 1 5, 2011
ATTACHMENT TO LICENSE AMENDMENT NO. 162 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following page of the Facility Operating License with the revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Remove Insert Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 2-1 2-1
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40, 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.0. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level Exelon Generation Company is authorized to operate the facility at reactor core power levels of 3458 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.162 ,are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Fire Protection (Section 9.5, SSER-2, -4)*
Exelon Generation Company shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report dated August 1983 through Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 4, ~, a4, 00, 92, -W8 162
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER. Low Pressure or Low Flow 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 785 psig or core flow less than 10% of rated fl ow.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 785 psig or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
THERMAL POWER, High Pressure and High Flow 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.09 for two recirculation loop operation and shall not be less than 1.12 for single recirculation loop operation with the reactor vessel steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With MCPR less than 1.09 for two recirculation loop operation or less than 1.12 for single recirculation loop operation and the reactor vessel steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 pSig.
APPLICABILITY: OPERATION CONDITIONS 1, 2, 3, and 4.
ACTION:
With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure less than or equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
LIMERICK - UNIT 2 2-1 Amendment No. +4, &J, &+, ~, ++/-4,
.f.H,162
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 162 TO FACILITY OPERATING LICENSE NO. NPF-85 EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNIT 2 DOCKET NO. 50-353
1.0 INTRODUCTION
By letter dated December 15, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103500180), supplemented by letters dated February 17, 2011 (ADAMS Accession No. ML110490572), and March 17,2011 (ADAMS Accession No. ML110770184), Exelon Generation Company, LLC (Exelon, the licensee) requested changes to the Technical Specifications (TSs) for Limerick Generating Station (LGS), Unit 2. The supplements clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 1, 2011 (76 FR 5620).
The submittal seeks to revise TS 2.1, "Safety Limits," to reflect revised Safety Limit Minimum Critical Power Ratio (SLMCPR) values listed in TS 2.1.2 and calculated for operating Cycle 12.
The SLMCPR analysis establishes SLMCPR values that will ensure that during normal operation and during abnormal operational transients, at least 99.9 percent of all fuel rods in the core do not experience transition boiling if the limit is not violated. The SLMCPRs are calculated to include cycle specific parameters.
The NRC staff has completed its review and finds that the requested TS modifications are acceptable, as discussed in this safety evaluation.
2.0 REGULATORY EVALUATION
The purpose of the SLMCPR is to ensure that specified acceptable fuel design limits (SAFDLs) are not exceeded during steady state operation and analyzed transients. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environment. The integrity of this cladding barrier is related to its relative freedom from perforations or cracking.
Fuel cladding perforations can result from thermal stresses, which can occur from reactor operation significantly above design conditions. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling have been used to mark the beginning of the region in which fuel cladding damage could occur.
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 36, 'Technical specifications," paragraph (c)(1), requires that power reactor facility TS include safety limits for
-2 process variables that protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The fuel cladding integrity SLMCPR is established to assure that at least 99.9 percent of the fuel rods in the core do not experience boiling transition during normal operation and abnormal operating transients. Thus, the SLMCPR is required to be contained in TS.
The NRC staff used 10 CFR Part 50, Appendix A, Criterion 10 (GDC-10), "Reactor Design," and NUREG-0800, "Standard Review PI.an for the Review of Safety Analysis Reports for Nuclear Power Plants," as evaluation criteria for the proposed license amendment request (LAR).
GDC-10 states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that SAFDLs are not exceeded.
As described in the LGS Updated Final Safety Analysis Report, Section 3.1, LGS meets the requirements of GDC-1 O. NUREG-0800, provides guidance on the acceptability of the reactivity control systems, the reactor core and fuel system design. Specifically, Section 4.2, "Fuel System Design," specifies all fuel damage criteria for evaluation of whether fuel designs meet the SAFDLs. Section 4.4, "Thermal Hydraulic Design," provides guidance on the review of thermal-hydraulic design in conforming to GDC-1 0 and the fuel design criteria established in Section 4.2.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes The submittal seeks to revise TS 2.1.2 to reflect revised SLMCPR values for operating Cycle 12.
Future operation beyond Cycle 12 would have to evaluate the TS SLMCPR values in accordance with normal core design processes to determine if they remain at the appropriate levels. The SLMCPR values in TS 2.1.2 are proposed to change from 1.07 to 1.09 for two recirculation loop operation, and to change from 1.09 to 1.12 for single loop operation. These SLMCPR values are applicable when the reactor steam dome pressure is greater than 785 psig
[pounds per square inch gauge] and core flow is greater than 10 percent of rated core flow.
3.2 NRC Staff Evaluation The licensee described the methodology to calculate the new SLMCPR values for the TS in its submittal and supplement. The Cycle 12 SLMCPR analysis was performed by Global Nuclear Fuel (GNF) using plant- and cycle-specific fuel and core parameters, and NRC approved methodologies, including the following:
- NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR II)," Revision 16, October 2007
- NEDC-32505P-A, "R-Factor Calculation Method for GE11, GE12 and GE13 Fuel,"
Revision 1, July 1999
- NEDC-32601 P-A, "Methodology and Uncertainties for Safety Limit MCPR Evaluations,"
August 1999
August 1999
-3
- NEDO-10958P-A, "General Electric BWR [Boiling-Water Reactor] Thermal Analysis Basis (GETAB): Data, Correlation, and Design Application," January 1977 The LGS Unit 2, Cycle 12 reactor core design includes 276 fresh GNF2 fuel assemblies. The licensee addressed the applicability of the above approved methodologies to the associated SLMCPR calculation since the data bases for the GNF2 fuel were not included in those approved methodologies. The NRC staff reviewed the licensee's justification for the applicability of the above approved methodologies to LGS Unit 2, Cycle 12 including a review of the NRC staffs report dated September 25, 2008, "Audit Report for Global Nuclear Fuels GNF2 Advanced Fuel Assembly Design GESTAR II Compliance Audit," (ADAMS Accession No. ML081630579). This report was based on the GESTAR II compliance report for GNF2 fuel 1 and concluded that the justification is acceptable because GNF2 fuel meets the requirements as specified in the limitations and conditions of the approved methodologies.
The licensee addressed the final core loading pattern selection for LGS Unit 2, Cycle 12 operation with respect to the combination of the input parameters such as cycle energy requirements, thermal limit margins, reactivity margins, discharge exposure limitations and other limits, as well as desired control rod patterns, and channel distortion minimization. The SLMCPR calculation process was addressed with respect to the uncertainties associated with R-Factor, core flow rate and the Local Power Range Monitor update/calibration interval. The licensee also addressed the bundle groupings for both two-loop operation and single loop operation SLMCPR calculations, along with the number of bundles in the group, their contribution to percent number of rods subject to boiling transition (NRSBT) and group average fuel assembly exposure for Cycle 12. Finally, the licensee provided an updated two-loop power/flow map for Cycle 12 operation including stability Option III features of the scram region and controlled entry region for backup stability protection.
The NRC staff reviewed the information presented in the submittal and supplemental information and concluded that the licensee provided satisfactory data and methodology descriptions. The NRC staff determined that the proposed revisions to the TS SLMCPR values for LGS Unit 2, Cycle 12 operation, from 1.07 to 1.09 for two recirculation loop operation and from 1.09 to 1.12 for single loop operation, are acceptable for the following reasons:
(1) Approved methodologies are used with acceptable justification for the method deviation and adjusted uncertainties relating to R-Factor and Traversing Incore probe (TIP) reading.
(2) The GNF2 data contained in Figure 5 of the submittal, as supplemented by letter dated February 17, 2011, provides sufficient evidence of an acceptable relationship between MCPR Importance Factor (MIP) and Critical Power Ratio (CPR) margin.
(3) Qualitative descriptions of the final core loading pattern and critical power analysis are provided and considered acceptable.
- 1. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, March 2007, and GEXl17 Correlation for GNF2 Fuel, NEDC-33292P. March 2007," FlN-2007 011, dated March 14, 2007 (ADAMS Accession No. Ml070780335)
-4 (4) A core map for Cycle 12 was provided and dominant fuel bundle locations were identified based on the LGS Unit 2 Cycle 12 SLMCPR calculation in terms of percent contribution to NRSBT.
(5) Mechanisms to push the SLMCPR increase into the higher range of expectations are identified, along with the result that the GNF2 fuel would dominate the SLMCPR calculation.
The NRC staff also reviewed the justification for the SLMCPR value of 1.09 for two recirculation loop operation and 1.12 for single loop operation using the approach stated in Revision 16 of the GESTAR-II methodology. Based on the review of the submittal, and the supplemental information, the NRC staff has concluded that the SLMCPR analysis for LGS Unit 2, Cycle 12 operation using the plant- and cycle-specific calculation in conjunction with the approved method is acceptable. The Cycle 12 SLMCPR will ensure that 99.9 percent of the fuel rods in the core will not experience boiling transition, which also conforms with GDC-10 regarding acceptable fuel design limits. The NRC staff has concluded that the justification for analyzing and determining the SLMCPR value of 1.09 for two recirculation loop operation and 1.12 for single recirculation loop operation for LGS Unit 2, Cycle 12 is acceptable, since approved methodologies were used in conjunction with assumption of a higher R-Factor uncertainty, performance of a bounding calculation at rated core power and minimum core flow, and an analysis on power shape for Cycle 12 operation which results in no fuel axial power shape penalty.
Based on the review above, and because the changes were analyzed based on NRC-approved methods using LGS Unit 2, cycle-specific inputs for the Cycle 12 fuel bundles, the NRC staff finds that the TS changes proposed in the LAR involving the SLMCPR values for both two loop and single loop operation, are acceptable for LGS Unit 2, Cycle 12 operation.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The NRC staff has determined that the amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (76 FR 5620). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b} no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
- 5
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: T. Huang Date: April 5, 2011
April 5, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNIT 2 -ISSUANCE OF AMENDMENT RE:
SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO.
ME5182)
Dear Mr. Pacilio:
The Commission has issued the enclosed Amendment No. 162 to Facility Operating License No.
NPF-85, for Limerick Generating Station (LGS), Unit 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 15, 2010 (Agencywide Documents Access and Management System Accession No. ML103500183),
supplemented by letters dated February 17, 2011 (ADAMS Accession No. ML110490572), and March 17,2011 (ADAMS Accession No. ML110770184).
The amendment consists of revisions to the TSs relating to the Safety Limit Minimum Critical Power Ratios (SLMCPRs). The changes result from a cycle specific analysis performed to support the operation of Limerick Generating Station, Unit 2, in the upcoming Cycle 12.
Specifically, the proposed TS changes will revise the SLMCPRs contained in TS 2.1.2 for two recirculation loop operation and single recirculation loop operation to reflect the changes in the cycle specific analysis.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely.
Ira!
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-353
Enclosures:
- 1. Amendment No. 162 to License No. NPF-85
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-2 Resource RidsNrrPMUomerick Resource RidsNrrLAABaxter Resource RidsNrrDorlDpr Resource THuang, NRR RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource LPL 1-2 R/F RidsOgcRp Resource RidsNrrDssSrxb Resource Amen d mentA ccesslon N0.: ML110750446
...via correspondence LPLI-2/PM LPLI-2/LA SRXB/BC OGC LPLI-2/BC MWright (NLO Name PBamford ABaxter (SUttle for) AUlses" HChernoff w/comments)
Date 3/21/2011 3/21/2011 14/2011 3131/2011 4/512011 Official Record Copy