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| {{#Wiki_filter:Information inhis report is provided for general informational purposes only and is subject to change without notice.) (For additional information contact Erika Lee at: erika.lee@nrc.gov)This RIS update is intended to clarify the guidance contained in previously issued RIS 2005-29. RIS 2005-29 was initially issued to discuss concerns with demonstrating that certain events would not escalate into more serious events. This RIS was initially intended to discuss technical specification definitions related to reactor coolant system pressure boundary leakage but was placed on hold pending industry development of Technical Specification Task Force (TSTF) Traveler 554, "Revise Reactor Coolant Leakage Requirements." The NRC was recently informed that industry no longer plans to submit TSTF Traveler 554 for review, therefore NRC is again evaluating whether to develop this RIS. | | {{#Wiki_filter:Summary Report of Open Generic Communication Projects (As Of 06/30/2018) |
| This RIS is intended to reiterate existing requirements related to dispositioning information pertaining to the capability of safety-related structures, systems, and components (SSC) to perform their safety functions. Also addressed are instances where a licensee becomes aware of information pertaining to the time period that a safety-related SSC is installed that may impact its ability to perform its safety function(s).This RIS is intended to remind licensees of the requirements regarding reporting human performance incidents under 10 CFR 50.73, "Licensee event report system," and how to properly report those matters. This RIS specifically focuses on 10 CFR 50.73 (b)(2)(ii)(J), which requires a narrative description for each human performance related root cause discussing the causes and circumstances. This RIS is intended to clarify the applicability of the single failure criterion as it relates to technical specification systems, structures and components with support systems not covered in technical specifications This RIS is intended to clarify the requirements for bare metal visual examination. This IN is intended to inform addressees of recent operating experience related to numerous dryout indications which occurred over multiple cycles at the Leibstadt Nuclear Power Plant (NPP), a BWR/6 in Switzerland. This RIS is intended to supply information to assist medical use licensees in complying with the current NRC requirements related to the use of electronic signatures in internal licensee electronic documents and to clarify what constitutes a signature on electronic documents that medical use licensees are required to sign and Information inhis report is provided for general informational purposes only and is subject to change without notice.) (For additional information contact Erika Lee at: erika.lee@nrc.gov)maintain. This RIS is intended to clarify the reporting requirements for nuclear facilities and equipment as required by 10 CFR 110.54 and the International Atomic Energy Agency for the Application of Safeguards in the United States.
| | Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.) |
| This RIS clarifies the National Source Tracking System (NSTS) Reporting requirements involving Category 1 or Category 2 sealed sources that a manufacturer identifies as bulk material. This RIS is intended to inform addressees about recent NRC findings involving vendors that provide basic components to NRC-licensed facilities for not adequately imposing the requirements of Appendix B "Quality Assurance Program Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 and 10 CFR Part 21, "Reporting of Defects and Noncompliance," to their suppliers in the procurement documents. This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC). This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities.
| | (For additional information contact Erika Lee at: erika.lee@nrc.gov) |
| This information notice is being issued to inform licensees of hazards from a high energy arc flash (HEAF) event resulting from the inadvertent introduction of foreign material to an energized switchgear bus during the application of fire protection material in the switchgear room. The force of the pressure wave caused by the HEAF breached the integrity of the fire door separating two safety-related switchgear rooms.
| | CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND |
| Information inhis report is provided for general informational purposes only and is subject to change without notice.) (For additional information contact Erika Lee at: erika.lee@nrc.gov)The intent of this RIS is to inform the addressees that on May 11, 2018, NRC issued Enforcement Guidance Memorandum 18-001, "Interim Guidance for Dispositioning Apparent Violations of Requirements for 10 CFR Part 34, 36, And 39 Activities Resulting from the Use of Direct Ion Storage Dosimetry During Licensed Activities," concerning dispositioning inspection findings related to use of direct ion storage dosimetry during NRC-licensed activities. The NRC is writing this information Notice to alert licensees and 10 CFR 50 Appendix B suppliers of the potential quality problems with Kobe Steel supplied materials
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| This was issued as IN 2018-07 on June 13, 2018. This was issued as IN 2018-08 on June 13, 2018.}} | | ==SUMMARY== |
| | (Mon) OPENED L2014-CRS- RIS RIS 2005-29 Rev 1 Anticipated Transients That Could Develop into More Serious Events 50.0 04/6/2014 0001 This RIS update is intended to clarify the guidance contained in previously issued RIS 2005-29. RIS 2005-29 was initially issued to discuss concerns with demonstrating that certain events would not escalate into more serious events. |
| | L2014-CRS- RIS Pressure Boundary Leakage 48.0 06/30/2014 0002 This RIS was initially intended to discuss technical specification definitions related to reactor coolant system pressure boundary leakage but was placed on hold pending industry development of Technical Specification Task Force (TSTF) Traveler 554, Revise Reactor Coolant Leakage Requirements. The NRC was recently informed that industry no longer plans to submit TSTF Traveler 554 for review, therefore NRC is again evaluating whether to develop this RIS. |
| | L2015-CRS- RIS Safety-Related SSCs in Service Beyond Service Life 40.0 02/03/2015 0001 This RIS is intended to reiterate existing requirements related to dispositioning information pertaining to the capability of safety-related structures, systems, and components (SSC) to perform their safety functions. Also addressed are instances where a licensee becomes aware of information pertaining to the time period that a safety-related SSC is installed that may impact its ability to perform its safety function(s). |
| | L2016-CRS- RIS Identifying and Reporting Human Factor Incidents Under 10 CFR 50.73 29.0 01/13/2016 0001 This RIS is intended to remind licensees of the requirements regarding reporting human performance incidents under 10 CFR 50.73, Licensee event report system, and how to properly report those matters. This RIS specifically focuses on 10 CFR 50.73 (b)(2)(ii)(J), which requires a narrative description for each human performance related root cause discussing the causes and circumstances. |
| | L2016-CRS- RIS Functionality of Non-Tech Spec Support Systems as They Relate to Operability of Tech Spec 20.0 10/11/2016 0004 Systems This RIS is intended to clarify the applicability of the single failure criterion as it relates to technical specification systems, structures and components with support systems not covered in technical specifications L2017-CRS- RIS Clarification of Visual Examination Requirements for Reactor Upper Heads to Detect Signs of 14.0 04/05/2017 0040 Leakage This RIS is intended to clarify the requirements for bare metal visual examination. |
| | L2017-CRS- IN Boiling-Water Reactor Dryout Indications Occurring During Normal Operation 11.0 07/28/2017 0046 This IN is intended to inform addressees of recent operating experience related to numerous dryout indications which occurred over multiple cycles at the Leibstadt Nuclear Power Plant (NPP), a BWR/6 in Switzerland. |
| | L2017-CRS- RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation 10.0 08/24/2017 0048 This RIS is intended to supply information to assist medical use licensees in complying with the current NRC requirements related to the use of electronic signatures in internal licensee electronic documents and to clarify what constitutes a signature on electronic documents that medical use licensees are required to sign and |
| | |
| | Summary Report of Open Generic Communication Projects (As Of 06/30/2018) |
| | Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.) |
| | (For additional information contact Erika Lee at: erika.lee@nrc.gov) |
| | CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND |
| | |
| | ==SUMMARY== |
| | (Mon) OPENED maintain. |
| | L2017-CRS- RIS Reporting Requirements for Components Exported Under General License Provisions 8.0 10/03/2017 0004 This RIS is intended to clarify the reporting requirements for nuclear facilities and equipment as required by 10 CFR 110.54 and the International Atomic Energy Agency for the Application of Safeguards in the United States. |
| | L2018-CRS- RIS Clarification for Reporting Transactions to the National Source Tracking System Involving 5.0 01/25/2018 0003 Encapsulated Bulk Material This RIS clarifies the National Source Tracking System (NSTS) Reporting requirements involving Category 1 or Category 2 sealed sources that a manufacturer identifies as bulk material. |
| | L2018-CRS- RIS Supplier Oversight From Recent Vendor Inspections 5.0 01/22/2018 0004 This RIS is intended to inform addressees about recent NRC findings involving vendors that provide basic components to NRC-licensed facilities for not adequately imposing the requirements of Appendix B Quality Assurance Program Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50 and 10 CFR Part 21, Reporting of Defects and Noncompliance, to their suppliers in the procurement documents. |
| | L2018-GEN- IN Evaluations Supporting Changes to Plant Configuration 3.0 03/29/2018 0000 This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC). |
| | L2018-GEN- IN Duties and Responsibilities of Armed Responders 3.0 03/29/2018 0001 This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities. |
| | L2018-GEN- IN Foreign Material from Installation of Thermo-Lag 770-1 Results in High Energy Arc Flash and Damage 2.0 04/19/2018 0002 to Fire Door This information notice is being issued to inform licensees of hazards from a high energy arc flash (HEAF) event resulting from the inadvertent introduction of foreign material to an energized switchgear bus during the application of fire protection material in the switchgear room. The force of the pressure wave caused by the HEAF breached the integrity of the fire door separating two safety-related switchgear rooms. |
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| | Summary Report of Open Generic Communication Projects (As Of 06/30/2018) |
| | Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.) |
| | (For additional information contact Erika Lee at: erika.lee@nrc.gov) |
| | CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND |
| | |
| | ==SUMMARY== |
| | (Mon) OPENED L2018-GEN- RIS Note of Issuance of EGMUse of Direct Ion Storage Dosimetry During Licensing Activities 1.5 05/04/2018 0003 The intent of this RIS is to inform the addressees that on May 11, 2018, NRC issued Enforcement Guidance Memorandum 18-001, Interim Guidance for Dispositioning Apparent Violations of Requirements for 10 CFR Part 34, 36, And 39 Activities Resulting from the Use of Direct Ion Storage Dosimetry During Licensed Activities, concerning dispositioning inspection findings related to use of direct ion storage dosimetry during NRC-licensed activities. |
| | L2018-GEN- IN Kobe Steel Quality Assurance Record Falsification .5 06/11/2018 0004 The NRC is writing this information Notice to alert licensees and 10 CFR 50 Appendix B suppliers of the potential quality problems with Kobe Steel supplied materials |
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| | Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND |
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| | ==SUMMARY== |
| | Date Opened Date Closed L2017- IN Pump/Turbine Bearing Oil Sight Glass Problems 12/01/2017 06/13/2018 CRS-0065 This was issued as IN 2018-07 on June 13, 2018. |
| | L2018- IN Failure to Enter the Required Technical Specification Action Statement for 01/23/2018 06/13/2018 CRS-0002 Operation During Recent Surveillance Testing While Using a Reactor Protection System Test Box This was issued as IN 2018-08 on June 13, 2018.}} |
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Category:Report
MONTHYEARML24204A2422024-11-0101 November 2024 Response to Ms. Carrie Fosaaen, Request for the NRC Action to Promptly Enable Construction of ASME Code Items Without an Owner ML24208A0452024-10-17017 October 2024 OMB-3150-0011 Final 2024 Collection Renewal, 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities - Supporting Statement Section 4 ML24211A1672024-10-0101 October 2024 OMB-3150-0039 Final 2024 Collection Renewal 10 CFR Part 140, Financial Protection Requirements and Indemnity Agreements - Supporting Statement ML24275A0752024-09-30030 September 2024 TLR-RES/DE/REB-2024-16, Integration of Safety, Security, and Safeguards During Design and Operations - a Technical Assessment and Regulatory Considerations for Advanced Reactor and Advanced Fuel Fabrication Facilities ML24197A1312024-09-0909 September 2024 NUREG 1022 Rev 3 Supplement 2 Comment Resolution Memo.Docx ML24136A1352024-07-30030 July 2024 LRA - Record of Decision ML24142A2652024-05-30030 May 2024 The Report on the Effectiveness of Training at Operating Power Reactors for CY2023 ML23177A2532023-10-23023 October 2023 OMB 3150-0136, Final 2023 Collection Renewal Notices of Enforcement Discretion (Noeds) for Operating Power Reactors and Gaseous Diffusion Plants (NRC Enforcement Policy) - Supporting Statement ML23046A0962023-08-25025 August 2023 OMB 3150-0151, Draft 2023 Collection Renewal 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants - Supporting Statement ML23032A3182023-07-31031 July 2023 Rulemaking - Proposed Rule - Unofficial Redline of Proposed Rule Language for American Society of Mechanical Engineers 2021-2022 Code Editions Update ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML22133A0462022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Backfitting and Issue Finality Assessment for Fitness for Duty Drug Testing Requirements ML22133A0522022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Response to Public Comments for Fitness for Duty Drug Testing Requirements ML22241A0392022-09-22022 September 2022 737 Max Digital Lessons Learned Report ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML22032A0012022-02-28028 February 2022 Rulemaking; Proposed Rule; Unofficial Redline Rule Language for the Proposed Rule - Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout ML21291A0242021-11-0909 November 2021 Ground Rules for Regulatory Feasibility of Remote Operations of Nuclear Power Plants ML21278A0822021-10-0505 October 2021 2021 List of Leaks and Spills ML21137A3102021-05-25025 May 2021 TLR-CIB-09 ORNL-SPR-2021-1988 ML20091L9832021-05-0404 May 2021 SLR License ML21084A0412021-03-31031 March 2021 Tlr RES DE CIB-CMB-2021-04, Corrosion in Gas-Cooled Reactors ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML20304A4982020-10-30030 October 2020 Public Comment Resolutions-RG 1.200-10-30-draft ML20141L5002020-05-11011 May 2020 2020 List of Leaks and Spills ML20070M8862020-03-0303 March 2020 March 3, 2020 - Contested and Uncontested Hearing Processes for a Combined License (COL) Application ML19242E1922019-08-30030 August 2019 Fuel Burnup and Enrichment Extension Preparation Strategy SECY-16-0142, Final Rule: Mitigation of Beyond-Design-Basis Events Backfitting and Issue Finality Assessment2019-07-31031 July 2019 Final Rule: Mitigation of Beyond-Design-Basis Events Backfitting and Issue Finality Assessment ML19071A2252019-03-12012 March 2019 NRC Comments on Industry Clarifications FAQ 18-0017 3/12/19 ML19002A1842019-02-14014 February 2019 Regional RIDM Online Survey Results ML18347B1582019-01-25025 January 2019 Draft Action Plan for Advanced Manufacturing Technologies - 2019-01-25 ML19010A2752019-01-25025 January 2019 Draft Action Plan for Advanced Manufacturing Technologies - Appendices - 2019-01-25 ML18337A1102018-12-0303 December 2018 Summary Report of Open Generic Communications Projects (as of 11/30/2018) ML18311A3602018-11-0707 November 2018 NRC Comments on Appendix D Revision 0g Rev. 1 ML18274A0692018-10-0101 October 2018 Summary Report of Open Generic Communication Projects (as of 09/30/2018) ML18247A4502018-09-0404 September 2018 Summary Report of Open and Closed Generic Communications Projects as of 08/31/2018 ML18057A0052018-08-17017 August 2018 COMSECY-18-0016: Enclosure 1 - Rulemaking for Appendix H to 10 CFR Part 50 - Reactor Vessel Material Surveillance Program Requirements - Regulatory Basis ML18235A1652018-07-31031 July 2018 NRC Comments on NEI 96-07, Appendix D, July 2018 ML18183A4432018-07-0202 July 2018 Summary Report of Open Generic Communication Projects (as of 06/30/2018) 2024-09-09
[Table view]Some use of "" in your query was not closed by a matching "". Category:Administrative
MONTHYEARML18247A4502018-09-0404 September 2018 Summary Report of Open and Closed Generic Communications Projects as of 08/31/2018 ML18183A4432018-07-0202 July 2018 Summary Report of Open Generic Communication Projects (as of 06/30/2018) ML0633100912006-11-27027 November 2006 for the Record: Summary of Nrc'S Review of the Recent Security Issues at the South Texas Project Nuclear Power Plant ML0634701802006-04-0303 April 2006 Pilgrim: NRC Contact Report - Arrange Meeting with Town Personnel During May Site Audit (Intergovernmental) ML0117304452001-06-22022 June 2001 RAI, Transmittal of Staff Questions Related to Staff Review of MRP-44, Part 2 PWR Materials Reliability Program Interim Alloy 600 Safety Assessments for U.S. PWR Plants (MRP-44), Part 2: Reactor Vessel Top Head Penetrations, TP-1001491, Par 2018-09-04
[Table view]Some use of "" in your query was not closed by a matching "". Category:Report
MONTHYEARML24204A2422024-11-0101 November 2024 Response to Ms. Carrie Fosaaen, Request for the NRC Action to Promptly Enable Construction of ASME Code Items Without an Owner ML24208A0452024-10-17017 October 2024 OMB-3150-0011 Final 2024 Collection Renewal, 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities - Supporting Statement Section 4 ML24211A1672024-10-0101 October 2024 OMB-3150-0039 Final 2024 Collection Renewal 10 CFR Part 140, Financial Protection Requirements and Indemnity Agreements - Supporting Statement ML24275A0752024-09-30030 September 2024 TLR-RES/DE/REB-2024-16, Integration of Safety, Security, and Safeguards During Design and Operations - a Technical Assessment and Regulatory Considerations for Advanced Reactor and Advanced Fuel Fabrication Facilities ML24197A1312024-09-0909 September 2024 NUREG 1022 Rev 3 Supplement 2 Comment Resolution Memo.Docx ML24136A1352024-07-30030 July 2024 LRA - Record of Decision ML24142A2652024-05-30030 May 2024 The Report on the Effectiveness of Training at Operating Power Reactors for CY2023 ML23177A2532023-10-23023 October 2023 OMB 3150-0136, Final 2023 Collection Renewal Notices of Enforcement Discretion (Noeds) for Operating Power Reactors and Gaseous Diffusion Plants (NRC Enforcement Policy) - Supporting Statement ML23046A0962023-08-25025 August 2023 OMB 3150-0151, Draft 2023 Collection Renewal 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants - Supporting Statement ML23032A3182023-07-31031 July 2023 Rulemaking - Proposed Rule - Unofficial Redline of Proposed Rule Language for American Society of Mechanical Engineers 2021-2022 Code Editions Update ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML22133A0462022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Backfitting and Issue Finality Assessment for Fitness for Duty Drug Testing Requirements ML22133A0522022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Response to Public Comments for Fitness for Duty Drug Testing Requirements ML22241A0392022-09-22022 September 2022 737 Max Digital Lessons Learned Report ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML22032A0012022-02-28028 February 2022 Rulemaking; 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[Table view]Some use of "" in your query was not closed by a matching "". Category:Miscellaneous
MONTHYEARML24204A2422024-11-0101 November 2024 Response to Ms. Carrie Fosaaen, Request for the NRC Action to Promptly Enable Construction of ASME Code Items Without an Owner ML24208A0452024-10-17017 October 2024 OMB-3150-0011 Final 2024 Collection Renewal, 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities - Supporting Statement Section 4 ML24211A1672024-10-0101 October 2024 OMB-3150-0039 Final 2024 Collection Renewal 10 CFR Part 140, Financial Protection Requirements and Indemnity Agreements - Supporting Statement ML24197A1312024-09-0909 September 2024 NUREG 1022 Rev 3 Supplement 2 Comment Resolution Memo.Docx ML24136A1352024-07-30030 July 2024 LRA - Record of Decision ML24142A2652024-05-30030 May 2024 The Report on the Effectiveness of Training at Operating Power Reactors for CY2023 ML23177A2532023-10-23023 October 2023 OMB 3150-0136, Final 2023 Collection Renewal Notices of Enforcement Discretion (Noeds) for Operating Power Reactors and Gaseous Diffusion Plants (NRC Enforcement Policy) - Supporting Statement ML23032A3182023-07-31031 July 2023 Rulemaking - Proposed Rule - Unofficial Redline of Proposed Rule Language for American Society of Mechanical Engineers 2021-2022 Code Editions Update ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML22133A0462022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Backfitting and Issue Finality Assessment for Fitness for Duty Drug Testing Requirements ML22133A0522022-11-10010 November 2022 Response to SRM-M220323: Final Rule-Response to Public Comments for Fitness for Duty Drug Testing Requirements ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML22032A0012022-02-28028 February 2022 Rulemaking; 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Balsam, NRR to J. Crocker, NOAA Pilgrim: NRC Complete Responses to 4-9-12 NMFS Questions 2024-09-09
[Table view]Some use of "" in your query was not closed by a matching "". |
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Summary Report of Open Generic Communication Projects (As Of 06/30/2018)
Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.)
(For additional information contact Erika Lee at: erika.lee@nrc.gov)
CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND
SUMMARY
(Mon) OPENED L2014-CRS- RIS RIS 2005-29 Rev 1 Anticipated Transients That Could Develop into More Serious Events 50.0 04/6/2014 0001 This RIS update is intended to clarify the guidance contained in previously issued RIS 2005-29. RIS 2005-29 was initially issued to discuss concerns with demonstrating that certain events would not escalate into more serious events.
L2014-CRS- RIS Pressure Boundary Leakage 48.0 06/30/2014 0002 This RIS was initially intended to discuss technical specification definitions related to reactor coolant system pressure boundary leakage but was placed on hold pending industry development of Technical Specification Task Force (TSTF) Traveler 554, Revise Reactor Coolant Leakage Requirements. The NRC was recently informed that industry no longer plans to submit TSTF Traveler 554 for review, therefore NRC is again evaluating whether to develop this RIS.
L2015-CRS- RIS Safety-Related SSCs in Service Beyond Service Life 40.0 02/03/2015 0001 This RIS is intended to reiterate existing requirements related to dispositioning information pertaining to the capability of safety-related structures, systems, and components (SSC) to perform their safety functions. Also addressed are instances where a licensee becomes aware of information pertaining to the time period that a safety-related SSC is installed that may impact its ability to perform its safety function(s).
L2016-CRS- RIS Identifying and Reporting Human Factor Incidents Under 10 CFR 50.73 29.0 01/13/2016 0001 This RIS is intended to remind licensees of the requirements regarding reporting human performance incidents under 10 CFR 50.73, Licensee event report system, and how to properly report those matters. This RIS specifically focuses on 10 CFR 50.73 (b)(2)(ii)(J), which requires a narrative description for each human performance related root cause discussing the causes and circumstances.
L2016-CRS- RIS Functionality of Non-Tech Spec Support Systems as They Relate to Operability of Tech Spec 20.0 10/11/2016 0004 Systems This RIS is intended to clarify the applicability of the single failure criterion as it relates to technical specification systems, structures and components with support systems not covered in technical specifications L2017-CRS- RIS Clarification of Visual Examination Requirements for Reactor Upper Heads to Detect Signs of 14.0 04/05/2017 0040 Leakage This RIS is intended to clarify the requirements for bare metal visual examination.
L2017-CRS- IN Boiling-Water Reactor Dryout Indications Occurring During Normal Operation 11.0 07/28/2017 0046 This IN is intended to inform addressees of recent operating experience related to numerous dryout indications which occurred over multiple cycles at the Leibstadt Nuclear Power Plant (NPP), a BWR/6 in Switzerland.
L2017-CRS- RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation 10.0 08/24/2017 0048 This RIS is intended to supply information to assist medical use licensees in complying with the current NRC requirements related to the use of electronic signatures in internal licensee electronic documents and to clarify what constitutes a signature on electronic documents that medical use licensees are required to sign and
Summary Report of Open Generic Communication Projects (As Of 06/30/2018)
Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.)
(For additional information contact Erika Lee at: erika.lee@nrc.gov)
CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND
SUMMARY
(Mon) OPENED maintain.
L2017-CRS- RIS Reporting Requirements for Components Exported Under General License Provisions 8.0 10/03/2017 0004 This RIS is intended to clarify the reporting requirements for nuclear facilities and equipment as required by 10 CFR 110.54 and the International Atomic Energy Agency for the Application of Safeguards in the United States.
L2018-CRS- RIS Clarification for Reporting Transactions to the National Source Tracking System Involving 5.0 01/25/2018 0003 Encapsulated Bulk Material This RIS clarifies the National Source Tracking System (NSTS) Reporting requirements involving Category 1 or Category 2 sealed sources that a manufacturer identifies as bulk material.
L2018-CRS- RIS Supplier Oversight From Recent Vendor Inspections 5.0 01/22/2018 0004 This RIS is intended to inform addressees about recent NRC findings involving vendors that provide basic components to NRC-licensed facilities for not adequately imposing the requirements of Appendix B Quality Assurance Program Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50 and 10 CFR Part 21, Reporting of Defects and Noncompliance, to their suppliers in the procurement documents.
L2018-GEN- IN Evaluations Supporting Changes to Plant Configuration 3.0 03/29/2018 0000 This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC).
L2018-GEN- IN Duties and Responsibilities of Armed Responders 3.0 03/29/2018 0001 This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities.
L2018-GEN- IN Foreign Material from Installation of Thermo-Lag 770-1 Results in High Energy Arc Flash and Damage 2.0 04/19/2018 0002 to Fire Door This information notice is being issued to inform licensees of hazards from a high energy arc flash (HEAF) event resulting from the inadvertent introduction of foreign material to an energized switchgear bus during the application of fire protection material in the switchgear room. The force of the pressure wave caused by the HEAF breached the integrity of the fire door separating two safety-related switchgear rooms.
Summary Report of Open Generic Communication Projects (As Of 06/30/2018)
Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.)
(For additional information contact Erika Lee at: erika.lee@nrc.gov)
CAC/EPIDS AGE CAC/EPIDS NUMBER TITLE AND
SUMMARY
(Mon) OPENED L2018-GEN- RIS Note of Issuance of EGMUse of Direct Ion Storage Dosimetry During Licensing Activities 1.5 05/04/2018 0003 The intent of this RIS is to inform the addressees that on May 11, 2018, NRC issued Enforcement Guidance Memorandum 18-001, Interim Guidance for Dispositioning Apparent Violations of Requirements for 10 CFR Part 34, 36, And 39 Activities Resulting from the Use of Direct Ion Storage Dosimetry During Licensed Activities, concerning dispositioning inspection findings related to use of direct ion storage dosimetry during NRC-licensed activities.
L2018-GEN- IN Kobe Steel Quality Assurance Record Falsification .5 06/11/2018 0004 The NRC is writing this information Notice to alert licensees and 10 CFR 50 Appendix B suppliers of the potential quality problems with Kobe Steel supplied materials
Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND
SUMMARY
Date Opened Date Closed L2017- IN Pump/Turbine Bearing Oil Sight Glass Problems 12/01/2017 06/13/2018 CRS-0065 This was issued as IN 2018-07 on June 13, 2018.
L2018- IN Failure to Enter the Required Technical Specification Action Statement for 01/23/2018 06/13/2018 CRS-0002 Operation During Recent Surveillance Testing While Using a Reactor Protection System Test Box This was issued as IN 2018-08 on June 13, 2018.