ML18213A327
| ML18213A327 | |
| Person / Time | |
|---|---|
| Issue date: | 08/01/2018 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Lee E | |
| References | |
| Download: ML18213A327 (4) | |
Text
Summary Report of Open Generic Communication Projects (As Of 07/31/2018)
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-0001 RIS RIS 2005-29 Rev 1 Anticipated Transients That Could Develop into More Serious Events 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.
51 04/6/2014 L2014-CRS-0002 RIS Pressure Boundary Leakage 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.
49 06/30/2014 L2015-CRS-0001 RIS Safety-Related SSCs in Service Beyond Service Life 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).
41 02/03/2015 L2016-CRS-0001 RIS Identifying and Reporting Human Factor Incidents Under 10 CFR 50.73 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.
30 01/13/2016 L2016-CRS-0004 RIS Functionality of Non-Tech Spec Support Systems as They Relate to Operability of Tech Spec 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.
21 10/11/2016 L2017-CRS-0040 RIS Clarification of Visual Examination Requirements for Reactor Upper Heads to Detect Signs of Leakage This RIS is intended to clarify the requirements for bare metal visual examination.
15 04/05/2017 L2017-CRS-0046 IN Boiling-Water Reactor Dryout Indications Occurring During Normal Operation 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.
12 07/28/2017 L2017-CRS-0048 RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation 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 11 08/24/2017
Summary Report of Open Generic Communication Projects (As Of 07/31/2018)
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-0004 RIS Reporting Requirements for Components Exported Under General License Provisions 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.
9 10/03/2017 L2018-CRS-0004 RIS Supplier Oversight From Recent Vendor Inspections 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.
6 01/22/2018 L2018-CRS-0003 RIS Clarification for Reporting Transactions to the National Source Tracking System Involving 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.
6 01/25/2018 L2018-GEN-0000 IN Evaluations Supporting Changes to Plant Configuration This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC).
4 03/29/2018 L2018-GEN-0001 IN Duties and Responsibilities of Armed Responders This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities.
4 03/29/2018 L2018-GEN-0002 IN Foreign Material from Installation of Thermo-Lag 770-1 Results in High Energy Arc Flash and Damage 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.
3 04/19/2018
Summary Report of Open Generic Communication Projects (As Of 07/31/2018)
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-0003 RIS Note of Issuance of EGMUse of Direct Ion Storage Dosimetry During Licensing Activities 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.
2 05/04/2018 L2018-GEN-0004 IN Kobe Steel Quality Assurance Record Falsification 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.
1 06/11/2018 L2018-GEN-0005 RIS Pre-Application Communication and Scheduling for Accident Tolerant Fuel Licensing Submittals The staff has generated a list of questions regarding anticipated agency work in the area of accident tolerant fuels (ATF). This RIS will provide the venue for collecting that information.
0 07/30/2018 L2018-GEN-0006 IN Control Rod Drive Mechanism stuck rod at Électricité de France (EdF) in France The staff has shown that for Westinghouse plants that have thermal sleeves in the CRDM penetration tubes, the wear of the thermal sleeve flange against the tube could have potential consequences that were not previously considered. Recently, during a startup following a refueling outage at an Électricité de France (EdF), Belleville Unit 2, a flange remnant from a separated thermal sleeve became cocked and interfered with control rod movement.
0 07/31/2018
Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND
SUMMARY
Date Opened Date Closed