ML21008A477
| ML21008A477 | |
| Person / Time | |
|---|---|
| Issue date: | 01/06/2021 |
| From: | NRC/OCIO |
| To: | |
| References | |
| FOIA, NRC-2021-000027 | |
| Download: ML21008A477 (6) | |
Text
FOIA/PA NO: _2021-000027_
GROUP A RECORDS ALREADY PUBLICLY AVAILABLE
FOIA 2021-000027-Publicly Available-NCPs and DPOs Issued Between 1/1/09-11/9/20 NCP-2009-003 Draft Safety Culture Policy Statement ML091210497 NCP-2009-004 Processing Emergency Plan Reviews ML091671101 NCP-2009-006 TIA 2009-009 Reevaluation of LCO 3.0.4a at Palisades ML091830609 NCP-2009-007 TIA 2009-005 Reevaluation of LCO 3.0.4a at Palisades ML091830616 NCP-2010-001 Duane Arnold Heat Sink Triennial Inspection Report 50-331 002.
ML101720329 NCP-2010-002 Allegation Case NRR-2009-A-0014 Involving Offer of Early Alternate Dispute Resolution ML102090624 NCP-2010-004 Revised Models for Adoption of TSTF-513, Revision 2, Revised PWR Operability Requirement ML103480005 NCP-2010-005 St. Lucie - NRC Integrated Inspection Report 2010003 ML102100007 NCP-2010-007 V.C. Summer 2010-502 Inspection Report.
ML102520299 NCP-2010-010 NRC Information Notice 2011-02, Operator Performance Issues Involving Reactivity Management at Nuclear Power Plants.
ML110420293 NCP-2010-011 Advanced Final Safety Evaluation Report for the AP1000 Standard Design Certification Amendment - Chapter 7, "Instrumentation and Control".Non-Concurrence - Advanced Final Safety Evaluation Report for the AP1000 Standard Design Certification ML103620506 NCP-2010-012 AP1000 Instrumentation and Controls Designs Certification Amendment Advanced Final Safety Evaluation Report.
ML103630486 NCP-2011-002 Yucca Mountain Program ML112440329 NCP-2011-003 Yucca Mountain Program ML112440344 NCP-2011-004 Yucca Mountain Program ML112440351 NCP-2011-005 2011 LES Licensee Performance Letter and Enclosure ML110770438 NCP-2011-006 Draft Safety Evaluation for the Electric Power Research Institute's, (TR), (MRP) Report 1016596 (MRP-227), Revision 0, Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines ML110770162 NCP-2011-007 Regulatory Issue Summary 2005-02, Revision 1 ML11110A025 NCP-2011-008 Response to OIG Report OIG-11-A-08 (10 CFR Part 21 Implementation)
ML111310413 NCP-2011-009 Columbia Inspection Report 05000397/2011002, (Section 4OA2.3)
ML111370091 NCP-2011-012 Update on Yucca Mountain Program ML112291036 NCP-2011-013 Update on Yucca Mountain Program ML112291038 NCP-2011-014 South Texas Project Hydrology SER ML12348A249 NCP-2011-100 EGM-11-003, Enforcement Guidance Memorandum on Dispositioning Boiling Water Reactor Licensee Non-Compliance with Technical Specification Containment Requirements During Operations with a Potential for Draining the Reactor Vessel ML11277A281 NCP-2011-101 Inspection Report and Notices of Violation at LES 70-31031/2011-201 ML112800306 NCP-2011-102 Order Prohibiting Involvement in Licensed Activities-IA-11-032 ML12082A187 NCP-2012-001 Diablo Canyon Power Plant Inspection Report 202011005 ML12151A173 NCP-2012-004 Draft NUREG/CR 7130 Assessment of Uncertainties Associated with the BADGER Methodology ML12255A350 NCP-2012-008 NUREG-1022, Rev. 3, "Event Reporting Guidelines: 10 CFR 50.72 and 50.73" ML12363A061 NCP-2012-009 Endorsement of Electric Power Research Institute Final Draft Report 1025287, Seismic Evaluation Guidance ML13058A374
NCP-2013-002 Policy Options for Merchant (Non-Electric Utility) Plant Financial Qualifications ML13217A070 NCP-2013-003 Request for Exemption from 10 CFR 50.38 Requirements for Maine Yankee Atomic Power Company, Connecticut Yankee Atomic Power Company, and Yankee Atomic Electric Company (TAC NOS. L24538, L24565, AND L24566)
ML13228A225 NCP-2013-005 Regulatory Basis to Address Nuclear Regulatory Commission Near-Term Task Force Recommendation 8 ML13269A327 NCP-2013-006 Recommendation 8 Regulatory Basis ML13269A322 NCP-2013-010 Dresden Nuclear Power Station, Units 2 and 3; Report Nos.
05000237/2013407; 05000249/2013407 (DRS) and Results of Investigation Report No. 3-2012-020 ML13329A531 NCP-2013-012 Ongoing Staff Activities to Assess Regulatory and Technical Considerations for Power Reactor Subsequent License Renewal ML16180A047 NCP-2013-013 Staff Evaluation and Recommendation for Japan Lessons-Learned Tier 3 Issue on Expedited Transfer of Spent Fuel ML13282A632 NCP-2013-014 SRXB Input for the Byron and Braidwood MUR Safety Evaluation ML14052A431 NCP-2013-015 Next Generation Nuclear Plant - Assessment of Key Licensing Issues ML14126A242 NCP-2014-001 Proposed Amendment to Incorporate by Reference Institute of Electrical and Electronics Engineers Standard 603-2009, "Standard Criteria for Safety Systems for Nuclear Power Generating Stations" Into Title 10 of the Code of Federal Regulations, Section 50.55A ML14280A340 NCP-2014-003 Proposed Amendment to Incorporate by Reference Institute of Electrical and Electronics Engineers Standard 603-2009, "Standard Criteria for Safety Systems for Nuclear Power Generating Stations" Into Title 10 of the Code of Federal Regulations, Section 50.55A ML14280A367 NCP-2014-004 Proposed Amendment to Incorporate by Reference Institute of Electrical and Electronics Engineers Standard 603-2009, "Standard Criteria for Safety Systems for Nuclear Power Generating Stations" Into Title 10 of the Code of Federal Regulations, Section 50.55A ML14281A145 NCP-2014-005 Louisiana Energy Services, LLC, - NRC Inspection Report No.
70-3103/2013-008 ML15086A325 NCP-2014-007 Next Generation Nuclear Plant - Assessment of Key Licensing Issues ML14154A080 NCP-2014-010 SECY: Relationship Between Mitigating Strategies for Beyond-Design-Basis External Events and Reevaluation of Flooding Hazards ML14321A572 NCP-2014-011 SECY: Relationship Between Mitigating Strategies for Beyond-Design-Basis External Events and Reevaluation of Flooding Hazards ML14321A577 NCP-2014-012 ANS Grant regarding Alleged Prohibited Travel/Lodging/
Subsistence ML15159A889 NCP-2015-001 Proposed Amendment to Incorporate by Reference Institute of Electrical and Electronics Engineers Standard 603-2009, "Standard Criteria for Safety Systems for Nuclear Power Generating Stations" Into Title 10 of the Code of Federal Regulations, Section 50.55A ML15036A467 NCP-2015-002 Review of Lessons Learned from the San Onofre Steam Generator Tube Degradation Event ML15062A132 NCP-2015-003 Proposed Rule Mitigation of Beyond-Design-Basis Events (SECY Paper)
ML15091A646 NCP-2015-005 ISG on Evaluations of Uranium Recovery Facility Surveys of Radon and Radon Progeny in Air and Demonstrations of Compliance With 10 CFR 20.1301 ML19121A171 NCP-2015-006 Audit Report on Mitigating Strategies & Reliable Spent Fuel Pool Instrumentation ML15159A273 NCP-2015-007 Safety Evaluation Regarding Crystal River Unit 3 License Amendment Request ML15212A946 NCP-2015-009 Discussion of EEEB Comments on Vogtle 4b SE ML15322A197 NCP-2015-010 Final Rule: Emergency Core Cooling Systems Performance During Loss-of-Coolant Accidents ML16028A388 NCP-2015-011 Recommendations on Issues Related to Implementation of a Risk Management Regulatory Framework ML15348A046 NCP-2015-012 Amendment No. 171 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant ML16033A197 NCP-2015-013 NFS RAI on GL 2015-001 ML16034A462
NCP-2016-003 IMC 0308, Attachment 3, "Basis for the Significance Determination Process" ML16172A176 NCP-2016-004 Diablo Canyon Amendments for Risk-Informed, Performance-Based Fire Protection Program (NFPA 805)
ML16096A325 NCP-2016-005 Susquehanna License Amendment Adopting TSTF-425 ML16141A025 NCP-2016-009 SE on Topical Report MRP-335,r3 PWSCC Mitigation by Surface Stress Improvement ML16187A319 NCP-2016-010 Nine Mile Point Unit Amendment - Adoption of TSTF-425 ML16148A057 NCP-2016-011 Ginna-Amendment Re: License Amendment Request to Relocate Specific Surveillance Freq. Req.
ML16176A235 NCP-2016-012 Waterford-Issuance of Amendment Re: Adoption of TSTF-425, Rev. 3 ML16209A045 NCP-2016-013 Wolf Creek Inspection Report-Preliminary White Finding re:
EDGs ML16237A009 NCP-2016-014 JLD ISG on Mitigation Strategies for BDB External Events ML16295A104 NCP-2016-015 Columbia-Issuance of Amendment Re: Adoption of TSTF-425, Rev. 3 ML16298A131 NCP-2016-016 Harris-Issuance of Amendment Re: Adoption of TSTF-425, Rev.
3 ML16298A322 NCP-2016-017 Revised FAQ 08-0046 Retirement NEI Response Letter ML16327A451 NCP-2016-018 Mitigation of Beyond-Design-Basis Events Rule ML16312A020 NCP-2016-020 Indian Point Integrated Inspection Report ML17013A245 NCP-2016-021 Reactor Inspection Procedures ML16341C689 NCP-2016-022 North Anna 3 Final Safety Evaluation Report ML17011A203 NCP-2017-001 Perry Integrated Inspection Report ML17076A186 NCP-2017-004 Donald C. Cook, Nuclear Plant, Units 1 and 2-Issuance of Amendment Re: Adoption of TSIF-425, Rev. 3 ML17074A089 NCP-2017-005 Cooper Nuclear Station - Issuance of Amendment No. 258 Re:
Adoption of TSTF-425, Rev. 3.
ML17079A256 NCP-2017-006 Brunswick Steam Electric Plant-Re: Adoption of TSTF-425 ML17109A134 NCP-2017-008 Vogtle 4b LAR ML17193A323 NCP-2017-009 Response to Disputed NCV at VC Summer ML17230A129 NCP-2017-010 Grand Gulf Special Inspection Report ML17304A014 NCP-2017-011 Diablo Canyon Supplemental Inspection-Closeout of White Finding ML17271A438 NCP-2017-012 NRR Response Letter to David Lochbaum Concerning Palo Verde License Amendments 199 and 200 ML17269A048 NCP-2017-013 Watts Bar Integrated Inspection Report ML17326A235 NCP-2017-014 IMC 0611, "Power Reactor Inspection Reports" ML17353A319 NCP-2017-016 Vogtle Staff Review of Seismic PRA on NTTF Recommendation 2.1 ML18008A305 NCP-2018-001 Oconee Relief Request Safety Evaluation ML18060A028 NCP-2018-002 Final ASP Program Analysis-Precursor LaSalle County Station, Unit 2, HPCS System Inoperable ML18157A264 NCP-2018-003 Clarification of Regulatory Approaches for Lead Test Assemblies, from Brian Holian, NRC, to Pamela Cowan, NEI ML18151B016 NCP-2018-004 Response to Disputed Non-Cited Violation Documented in Palisades Nuclear PlantNRC Design Basis Assurance Inspection (Teams) Inspection Report 05000255/2017007 Withdrawal of Non-Cited Violation ML18337A440 NCP-2018-006 Oconee Single Failure Condition ML18311A013 NCP-2018-008 Safety Evaluation of Vogtle Tier 2* LAR ML18256A400 NCP-2018-009 TSTF-505, Provide Risk Informed Completion Times-RITSTF Initiative 4b, Rev 2 ML18310A175 NCP-2019-001 Amendment for the Oconee Physical Security Plan LAR ML19274B077 NCP-2019-002 Vogtle Electric Generating Plant, Units 3 and 4 - NRC Inspection Reports 05200025/2019010 and 05200026/2019010 ML20197A032 NCP-2019-004 NuScale Phase 4 Chapter 3 ML20049A058 NCP-2019-005 Monticello Nuclear Generating Plant - Follow-Up Inspection Regarding the Assessment and Management of Shutdown Risk ML19331A275 NCP-2019-006 LIC-500 Topical Report Process Revision 8 ML20044D226
NCP-2020-001 Safety Evaluation Report Related to the Subsequent License Renewal of Surry Power Station - Selective Leaching Op E Issue ML20066J465 NCP-2020-002 Safety Evaluation Report Related to the Subsequent License Renewal of Surry Power Station - Units 1 and 2 ML20066J740 NCP-2020-004 Draft Regulatory Guide DG-1363: Revision 4 of Regulatory Guide 1.105, "Setpoints for Safety-Related Instrumentation" ML20181A524 NCP-2020-005 RG 1.187 Draft Rev. 2: Guidance for Implementation of 10 CFR 50.59, Change, Tests and Experiments ML20197A381 NCP-2020-006 Phase 4 NuScale DC SER Chapters 6 and 15 ML20230A245 NCP-2020-008 Withdrawal of a Non-Cited Violation (NCV) Associated with the Failure to Qualify WPS [Welding Procedure Specification] in Accordance with Applicable Code, Involving Vogtle Units 3 and 4 ML20345A198 DPO-2009-001 Fire Protection NFPA 805 Additional Risk Associated with Previously Approved Actions ML101590266 DPO-2010-001 Interpretation of Categorical Exclusions in Part 51 ML11228A281 DPO-2011-001 Enforcement Policy Issues ML11234A302 DPO-2011-002 Inspection Access at LES Gas Centrifuge Facility ML12151A376 DPO-2012-001 Applicability of Reporting Requirements in 10 CFR 70.72 for Shaw Areva MOX Services ML13014A193 DPO-2012-002 Acceptability of AP1000 Shield Building ML19057A509 DPO-2012-003 Protection from External Flooding of Watts Bar Unit 1 ML13115A273 DPO-2013-001 Commercial Grade Dedication at Mixed Oxide Fuel Fabrication Facility ML13346A967 DPO-2013-002 Diablo Canyon Seismic Issues ML14252A743 DPO-2014-001 FAQ for Fire Protection (08-0048: "Fire Ignition Frequency)
ML15273A079 DPO-2014-002 Use of Conditional Core Damage Probability (CCDP) to Evaluate Performance Deficiencies that Cause Initiating Events ML14344A291 DPO-2014-003 November 20, 2014 Revision to IMC 0305, "Operating Reactor Assessment Program ML15194A444 DPO-2015-001 Significance of Yellow Finding at ANO-1 ML16061A362 DPO-2016-001 PRA Language in RG 1.174 and 1.200 ML17013A015 DPO-2016-002 Boral Degradation in Spent Fuel Casks ML17069A437 DPO-2016-004 FAQ for Fire Protection (08-0046, "Incipient Fire Detection Systems")
ML18066A700 DPO-2017-001 Approval of Emergency Amendment for Palo Verde Unit 3 ML17202G468 DPO-2017-002 Approval of Emergency Amendment for Palo Verde Unit 3 ML17202G468 DPO-2017-003 Grand Gulf NCV Involving Occupational Doses ALARA ML18269A345 DPO-2017-004 NEI Guidance on Closure of PRA Peer Review Facts and Observations ML18078A786 DPO-2017-005 DMNS Recordkeeping ML17297B585 DPO-2017-007 Operator Licensing Written Examinations-Tier 1 Test Items ML19350C551 DPO-2017-008 Dose Limits in Non-Vital Areas during Accidents ML18152B664 DPO-2017-009 Significance Determination for Loss of Decay Heat Removal at Grand Gulf ML19043A950 DPO-2017-010 Five Inspection Findings/NCVs at Cooper ML19078A362 DPO-2017-011 Documentation of a Finding with Insignificant to No Safety Significance Contrary to ROP Guidance ML18192A599
DPO-2018-001 Closure of a White Finding at Columbia ML19052A108 DPO-2018-002 NRC Response to NEI Concerning the Regulatory Path for Accident Tolerant Fuel (ATF) Lead Test Assemblies (LTAs)
ML19141A075 DPO-2018-003 Regulatory Framework Governing Power Reactor Licensee Security Plan Changes Submitted Under 10 CFR 50.54(p)(2)