|
---|
Category:Safety Evaluation
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System ML22140A1272022-05-25025 May 2022 Subsequent License Renewal Application Safety Evaluation Revision 1 Public ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16241A0002016-09-23023 September 2016 Mitigating Strategies and Spent Fuel Pool Instrumentation Safety Evaluation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML16035A5092016-03-0909 March 2016 Correction of Typographical Error in Safety Evaluation Associated with License Amendment Nos. 238 and 242 ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15161A5352015-06-24024 June 2015 Relief Request VR-01; Alternatives to Certain Inservice Testing Requirements of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML14293A0022014-10-21021 October 2014 Issuance of Safety Evaluation Regarding Relief Request RR-5 ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML14014A2052014-01-30030 January 2014 Issuance of Relief Request Regarding Risk-Informed Inservice Inspection Program for the Fifth 10-Year Inservice Inspection Interval ML13329A0422013-12-20020 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L3) ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13346A0402013-12-18018 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L2) ML13135A2712013-05-29029 May 2013 Safety Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements ML12251A1552012-11-23023 November 2012 Issuance of Amendment to Renewed Facility Operating License Revised Cyber Security Plan Implementation Schedule Milestone 6 2024-01-23
[Table view] Category:Technical Specifications
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-02-12012 February 2016 License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2015-0075, License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation2016-01-15015 January 2016 License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation ML15232A2082015-08-25025 August 2015 Correction Letter for Amendment Nos. 253 and 257 ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 NRC 2015-0027, Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee..2015-05-28028 May 2015 Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee.. ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14213A0032014-08-14014 August 2014 Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254 NRC 2014-0003, License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2014-07-0303 July 2014 License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0202 July 2014 License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding2013-06-0404 June 2013 License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013 Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013 License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012 License Amendment Request 270, Operations Manager Qualification Requirements NRC 2012-0033, License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 22012-04-30030 April 2012 License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 2 NRC 2011-0040, License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements2011-05-0303 May 2011 License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements NRC 2010-0181, Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS)2010-11-16016 November 2010 Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS) NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power Uprate2010-08-24024 August 2010 License Amendment Request 261, Supplement 7, Extended Power Uprate NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010 License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate NRC 2010-0040, License Amendment Request 261, Supplement 4 Extended Power Uprate2010-04-15015 April 2010 License Amendment Request 261, Supplement 4 Extended Power Uprate NRC 2009-0080, License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information2009-08-20020 August 2009 License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information NRC 2009-0045, Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)2009-04-17017 April 2009 Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab) NRC 2009-0030, License Amendment Request 261, Extended Power Uprate2009-04-0707 April 2009 License Amendment Request 261, Extended Power Uprate NRC-2008-0086, License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum2008-11-25025 November 2008 License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008 License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair NRC 2008-0018, License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification2008-03-31031 March 2008 License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification NRC 2008-0014, Pressure and Temperature Limits Report2008-02-27027 February 2008 Pressure and Temperature Limits Report ML0804303372008-02-26026 February 2008 Technical Specification ML0804303942008-02-19019 February 2008 Tech Spec Page for Amendments 231 and 236 Deletion of Containment Purge Valve Surveillance Requirement ML0731803152007-11-16016 November 2007 Tech Spec Page for Amendments 230 and 235 TSTF- 491, Revision 2, Removal of Main Steam and Feedwater Valve Isolation Times Technical Specification 3.7.2 ML0721802192007-10-18018 October 2007 Technical Specifications, Revises TS 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) to Add the Ferret Code as an Approved Methodology for Determining RCS Pressure and Temperature Limits NRC 2007-0051, License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item..2007-06-29029 June 2007 License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item.. ML0709502652007-04-0404 April 2007 Technical Specification Pages Steam Generator Tube Repair in the Tubesheet Amendment ML0705103122007-02-15015 February 2007 Tech Spec Pages for Amendments 224 and 230 Regarding Core Alterations NRC-2007-0003, Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program2007-01-19019 January 2007 Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations2006-10-23023 October 2006 License Amendment Request 246 - Deletion of Core Alterations ML0626804152006-09-18018 September 2006 Tech Spec Pages to Correction to Amendment 223 Regarding Steam Generator Tube Integrity ML0623501982006-08-22022 August 2006 Technical Specifications, Steam Generator Tube Integrity, MD0194 & MD0195 L-HU-06-029, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-07-13013 July 2006 Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006 LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program ML0616001172006-06-0808 June 2006 Technical Specifications - Issuance of Amendments Inservice Testing Program L-HU-06-023, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-11011 May 2006 Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity NRC-2006-0032, License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals2006-03-0606 March 2006 License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-02-16016 February 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity 2024-01-23
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18345A1102019-03-26026 March 2019 Redacted Version, Issuance of Amendment Nos. 263 and 266 for Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17130A9352017-06-27027 June 2017 Correction Letter for Amendment Nos. 258 and 262 Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML16349A0802017-01-30030 January 2017 Issuance of Amendments for Elimination of Technical Specifications 3.7.14, Primary Auxiliary Building Ventilation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15028A1822015-02-12012 February 2015 Correction of Typographical Error Incurred During Prior License Amendment ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements ML12251A1552012-11-23023 November 2012 Issuance of Amendment to Renewed Facility Operating License Revised Cyber Security Plan Implementation Schedule Milestone 6 ML1135401472012-01-30030 January 2012 Issuance of Amendment to Revise Technical Specification Operating Limits to Include Measurement Uncertainty ML1103200602011-03-25025 March 2011 (Pbnp), Units 1 and 2 - Issuance of License Amendments Revision of Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrumentation Setpoints ML0825408832008-10-0707 October 2008 Issuance of License Amendment, Technical Specification 5.5.8 and 5.6.8 ML0809503412008-07-14014 July 2008 Issuance of Amendments Deletion of E Bar Definition and Revision of Reactor Coolant System Specific Activity ML0803803562008-02-26026 February 2008 Issuance of Amendments Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0724101042007-11-16016 November 2007 Issuance of Amendments 230 and 235 TSTF- 491, Revision 2, Removal of Main Steam and Feedwater Valve Isolation Times Technical Specification 3.7.2 ML0721801912007-10-18018 October 2007 License Amendment, Revises TS 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) to Add the Ferret Code as an Approved Methodology for Determining RCS Pressure and Temperature Limits ML0726801932007-09-28028 September 2007 License Pages - Ownership and Operating Authority ML0722800022007-08-16016 August 2007 Revised Pages of Facility Operating License DPR-24 and DPR-27 B.5.b ML0720803942007-07-31031 July 2007 License Pages for the Transfer of Point Beach Ownership and Operating Authority ML0715601242007-07-31031 July 2007 Order Approving Transfer of License and Conforming Amendment Relating to the Point Beach Nuclear Plant ML0720803972007-07-31031 July 2007 License Pages for the Transfer of Operating Authority Prior to Sale ML0713006232007-05-10010 May 2007 Issuance of Amendments Regarding Review of Reactor Vessel Fracture Mechanics Analysis ML0708006252007-04-0404 April 2007 Amendment Steam Generator Tube Repair in the Tubesheet ML0706006082007-03-21021 March 2007 Issuance of Amendments 225 and 231, Loss of Power Diesel Generator ML0634500732007-02-15015 February 2007 License Amendments 224 and 230 Regarding Core Alterations ML0704302892007-02-0101 February 2007 Administrative Change Without Safety Evaluation ML0620502992006-08-22022 August 2006 License Amendment, Steam Generator Tube Integrity, MD0194 & MD0195 ML0612800132006-06-0808 June 2006 Issuance of Amendments Inservice Testing Program ML0535302092005-12-22022 December 2005 Renewed Facility Operating License No. DPR-24 ML0531100312005-12-22022 December 2005 Current Facility Operating License DPR-24, Tech Specs, Revised 05/07/2019 2024-01-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 29, 2013 Mr. Larry Meyer Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT RE: OPERATIONS MANAGER QUALIFICATION REQUIREMENTS (TAC NOS. ME9270 AND ME9271)
Dear Mr. Meyer:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 248 and 252 to Renewed Facility Operating License Nos. DPR-24 and DPR-27, for the Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated August 16, 2012.
The amendments revise Technical Specification 5.3.1, "Facility Staff Qualifications," regarding the qualification requirements for the Operations Manager at PBNP. Specifically, the change revises the requirement that the Operations Manager hold a senior reactor operator license at the time of appointment to the active position, to a requirement that the Operations Manager meet one of the following: (1) hold a Senior Operator license; (2) have held a Senior Operator license on a similar unit; or (3) have been certified for equivalent Senior Operator knowledge.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
~~---------
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosures:
- 1. Amendment No. 248 to DPR-24
- 2. Amendment No. 252 to DPR-27
- 3. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 License No. DPR-24
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by NextEra Energy Point Beach, LLC (the licensee) dated August 16, 2012, 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 4.B of the Renewed Facility Operating License No. DPR-24 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 248, are hereby incorporated in the renewed operating license. NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
- 2
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert D. Carlson, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and the Renewed Facility Operating License Date of issuance: January 29, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 License No. DPR-27
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by NextEra Energy Point Beach, LLC (the licensee) dated August 16, 2012, 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 4.B of the Renewed Facility Operating License No. DPR-27 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 252 are hereby incorporated in the renewed operating license NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
-2
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert D. Carlson, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of issuance: January 29, 2013
ATTACHMENT TO LICENSE AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following pages of the Renewed Facility Operating License Nos. DPR-24 and DPR-27, and Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT 3 3 Technical Specifications REMOVE INSERT 5.3-1 5.3-1
-3 D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach 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 E. Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
- 4. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:
A. Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 248, are hereby incorporated in the renewed operating license.
NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
Renewed License No. DPR-24 Amendment No. 248
-3 C. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed source for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E. Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
- 4. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:
A. Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 252, are hereby incorporated in the renewed operating license.
NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
Renewed License No. DPR-27 Amendment No. 252
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, for comparable positions, except:
a) The education and experience eligibility requirements for license applicants, and changes thereto, shall be those previously reviewed by the NRC, specifically those referenced in NRC Safety Evaluation letter dated October 24, 2003.
b) The Operations Manager shall meet one of the following:
i) Hold a Senior Operator's license, or ii) Have held a Senior Operator's license on a similar unit (PWR), or iii) Have been certified for equivalent Senior Operator knowledge.
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).
5.3.3 In the event the position of Health Physicist is vacated and the proposed replacement does not meet all the qualifications of TS 5.3.1, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual.
Point Beach 5.3-1 Unit 1 - Amendment No. 248 Unit 2 - Amendment No. 252
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AND AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
By letter dated August 16,2012 (Agencywide Documents Access and Management System Accession No. ML 12229AS81), NextEra Energy Point Beach. LLC (NextEra, the licensee) submitted an application for a license amendment to revise the Point Beach Nuclear Plant (PBNP) Technical Specifications (TSs). The proposed amendment would revise TS 5.3, "Facility Staff Qualifications," to clarify the required qualifications of the Operations Manager position. Specifically, the change would revise the requirement that the Operations Manager hold a senior reactor operator (SRO) license at the time of appointment to the active position to a requirement that the Operations Manager meet one of the following: (1) hold a Senior Operator license, or (2) have held a Senior Operator license on a similar unit (PWR) , or (3) have been certified for equivalent Senior Operator knowledge.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC) regulatory requirements pertaining to the content of the Technical Specifications are contained in Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36. The regulations in 10 CFR SO.36(c) include a section on Administrative Controls. The Administrative Controls section in 10 CFR SO.36(c)(S) are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
At PBNP, the Administrative Controls are located in Section 5.0 of the TSs. Section S.2.2(d).
states that either the Operations Manager or Assistant Operations Manager hold a Senior Enclosure
-2 Reactor Operator's license at PBNP, and Section 5.3.1 states that each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971.
The regulations in 10 CFR 50.54(1) requires, in part, that licensees " ... designate individuals to be responsible for directing the licensed activities of licensed operators. These individuals shall be licensed as Senior Operators pursuant to part 55 of this chapter." The licensee currently meets this requirement with the Assistant Operations Manager, who is directly responsible for the performance and conduct of the operating crew (licensed operators) on shift and is required by TS Section 5.2.2(d) to hold a Senior Operator license. The Assistant Operations Manager reports directly to the Operations Manager.
The Operations Manager is required by TS Section 5.3.1 and ANSI N18.1-1971 to hold a senior operator license for the Point Beach Nuclear Plant at the time of appointment to the active position. The individual designated to be responsible for directing the licensed activities of license operators, be it the Operations Manager or Assistant Operations Manager, must maintain this license current in order to meet 10 CFR 50.54(1).
3.0 TECHNICAL EVALUATION
The Administrative Controls section of the PBNP TSs currently provides the requirements for station staff that relate to the organization and management as specified in 10 CFR 50.36( c).
Currently, TS Section 5.3.1 requires that the Operations Manager hold an SRO license at PBNP. The proposed change will specify that the Operations Manager shall meet one of the following: 1) hold a Senior Operator's license, or 2) have held a Senior Operator's license on a similar unit (PWR), or 3) have been certified for equivalent Senior Operator knowledge.
This change is consistent with ANSI/ANS-3.1-1993, "Selection, Qualification, and Training of Personnel for Nuclear Power Plants," Section 4.2.2, Special Requirements (1 )(a), (b) and (c) which was endorsed by Regulatory Guide (RG)1.8, Revision 3, "Qualification and Training of Personnel for Nuclear Power Plants." Additionally, ANSI/ANS-3.1-1993 specifies that if the Operations Manager does not hold a Senior Operator license, then the Operations Middle Manager (equivalent to the Assistant Operations Manager for PBNP) will hold a Senior Operator license. Current TS Section 5.2.2.d requires that either the Operations Manager or the Assistant Operations Manager shall hold an SRO license at Point Beach. Although PBNP is not committed to ANSI/ANS-3.1-1993, they will meet the Special Requirements for the Operations Manager as specified in this standard based on their revised TS Section 5.3.1 and the existing TS Section 5.2.2.d. Therefore, the proposed changes to TS Section 5.3.1 are consistent with RG 1.8, Revision 3.
The current PBNP TS Section 5.3.1 only requires the Operations Manager to have held an SRO license prior to assuming the Operations Manager position. If the PBNP Senior Operator license is not current, the Operations Manager would not meet the 10 CFR 50.54(1) requirements for directing the licensed activities of licensed operators since 10 CFR 50.54(1) requires that individual to be a licensed Senior Operator. In this case, the Assistant Operations Manager will meet this requirement based on TS Section 5.2.2.d, which requires the Assistant Operations Manager to hold an SRO license. The proposed change provides an allowance for the Operations Manager to hold a Senior Operator license and, if this option is used, then the Operations Manager would meet the requirements of 10 CFR 50.54(1). Additionally, the
-3 proposed change provides an option to have held a Senior Operator license on a similar unit (PWR) or have been certified for equivalent Senior Operator knowledge. These options would not meet the 10 CFR 50.54(1) requirements for the Operations Manager; however, as discussed above, the Assistant Operations Manager would then meet this requirement. In all cases, the proposed change does not affect PBNP's ability or responsibility to meet the requirement of 10 CFR 50.54(1).
In its August 16, 2012, submittal, the licensee stated that the Operations Manager is responsible for establishing high standards and expectation for operations activities and that the Assistant Operations Manager is directly responsible for the performance and conduct of the operating crews on watch (NRC licensed operators). Since the Assistant Operations Manager retains responsibility for directing the licensed operators which cannot be delegated to a non-licensed individual, the requirements of 10 CFR 50.54(1) are met.
The proposed change provides additional alternatives for the Operations Manager to meet experience requirements, yet still retains the required Senior Operator knowledge for a manager level individual. Additionally, the licensee stated that administrative controls are in place to prevent unlicensed personnel from directing the licensed activities of licensed operators, including the situation where the Assistant Operations Manager is unexpectedly unable to perform his duties.
Given that the proposed change is consistent with RG 1.8, Revision 3, and will continue to meet the regulatory requirements of 10 CFR 50.54(1), the NRC staff finds the proposed change to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Wisconsin State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). 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.
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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the
-4 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Currie Date: January 29, 2013
Mr. Larry Meyer January 29, 2013 Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241 SURIECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT RE: OPERATIONS MANAGER QUALIFICATION REQUIREMENTS (TAC NOS. ME9270 AND ME9271)
Dear Mr. Meyer:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 248 and 252 to Renewed Facility Operating License Nos. DPR-24 and DPR-27, for the Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated August 16, 2012.
The amendments revise Technical Specification 5.3.1, "Facility Staff Qualifications,>> regarding the qualification requirements for the Operations Manager at PBNP. Specifically, the change revises the requirement that the Operations Manager hold a senior reactor operator license at the time of appointment to the active position, to a requirement that the Operations Manager meet one of the following: (1) hold a Senior Operator license; (2) have held a Senior Operator license on a similar unit; or (3) have been certified for equivalent Senior Operator knowledge.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosures:
- 1. Amendment No. 248 to DPR-24
- 2. Amendment No. 252 to DPR-27
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC RidsOgcRp Resource SCurrie, NRR LPL3-1 rtf RidsNrrDorlLpl3-1 Resource RidsNrrDirslolb Resource RidsNrrPMPointBeach Resource RidsRgn3MailCenter Resource RidsNrrDssStsb Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource Accession Number: ML12362A009 PL3-1/PM DORLILA SFigueroa JMcHaie
- RElliolt DRoth RCarlson TBeitz
~----r--------+--~----r-------
12127/12 09/08/2011 12/31/12 01/15/13 01/24/13 01129113
~----~------~--------~-O~F~F~IC~I~ALRECORDSCOPY