ML18121A130
| ML18121A130 | |
| Person / Time | |
|---|---|
| Issue date: | 05/01/2018 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Lee E | |
| References | |
| Download: ML18121A130 (4) | |
Text
Summary Report of Open Generic Communication Projects (As Of 04/30/2018)
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 MF3949 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.
48.0 04/6/2014 MF4346 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.
46.0 06/30/2014 MF5661 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).
38.0 02/03/2015 MF7230 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.
27.0 01/13/2016 MF8453 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 17.0 10/11/2016 MF9464 RIS Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, Revision 1, NEI 101-01: A Revision of EPRI TR-102348 to Reflect Changes to the 10 CFR 50.59 Rule, Rev. 1 This supplement to RIS 2002-22 is intended to clarify the NRCs endorsement of NEI 01-01 by providing additional guidance for the qualitative assessment used to provide reasonable assurance that a digital modification will exhibit a low likelihood of failure.
12.0 03/27/2017 MF9558 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.
12.0 04/05/2017
Summary Report of Open Generic Communication Projects (As Of 04/30/2018)
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 MG0020 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.
8.0 07/28/2017 MG0146 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 maintain.
7.0 08/24/2017 L2017-CRS-0062 RIS Supplier Oversight Issues Identified During NRC Vendor Inspections This IN is intended to make addressees aware of recent experiences related inadequate oversight of suppliers that provide basic components to NRC-licensed facilities.
6.0 10/02/2017 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.
6.0 10/03/2017 L2017-CRS-0065 IN Pump/Turbine Bearing Oil Sight Glass Problems This IN will highlight recent operating experience issues involving bearing oil sight classes and resulting in damaged pump or turbine bearings.
4.0 12/01/2017 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.
3.0 01/22/2018 L2018-CRS-0002 IN Failure to Enter the Required Technical Specification Action Statement for Operation During Recent Surveillance Testing While Using a Reactor Protection System Test Box This IN is intended to inform addressees of recent instances where operators of boiling water reactors allowed multiple contacts in the reactor protection system circuitry to be bypassed without entering the appropriate action statement required by the licensees technical specifications. These conditions existed during quarterly surveillance testing of main steam isolation valve and turbine stop valve logic.
3.0 01/23/2018 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.
3.0 01/25/2018
Summary Report of Open Generic Communication Projects (As Of 04/30/2018)
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 L-2018-GEN-0001 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).
1.0 03/29/2018 L-2018-GEN-0002 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.
1.0 03/29/2018 L-2018-CRS-XXXX 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.
.1 04/19/2018
Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND
SUMMARY
Date Opened Date Closed L2017-CRS-0064 IN Process Assumptions Resulting in Unanalyzed and Improperly Analyzed Conditions Related to Long-Term Fissionable Material Accumulation in Fuel Cycle Facilities This was issued as IN 2018-05, Long-Term Fissile Material Accumulation Due to Unanalyzed or Improperly Analyzed Conditions at Fuel Cycle Facilities, on March 26, 2018.
11/15/2017 03/26/2018 L2018-CRS-0001 RIS Preparation and Scheduling of Operator Licensing Examinations This was issued as RIS 2018-02 on March 26, 2018.
01/23/2018 03/26/2018 L2018-CRS-0000 IN Inadequate Management Measures for Process Isolation Controls Designated as Items Relied on for Safety This was issued as IN 2018-06 on April 10, 2018.
01/19/2018 04/10/2018