ML18003A183
| ML18003A183 | |
| Person / Time | |
|---|---|
| Issue date: | 01/02/2018 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Lee E | |
| References | |
| Download: ML18003A183 (4) | |
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Summary Report of Open Generic Communication Projects (As Of 12/31/2017)
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 44.0 04/6/2014 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.
MF4346 RIS Pressure Boundary Leakage 42.0 06/30/2014 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.
MF5661 RIS Safety-Related SSCs in Service Beyond Service Life 34.0 02/03/2015 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).
MF7230 RIS Identifying and Reporting Human Factor Incidents Under 10 CFR 50.73 23.0 01/13/2016 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.
MF8453 RIS Functionality of Non-Tech Spec Support Systems as They Relate to Operability of Tech Spec 13.0 10/11/2016 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 MF9358 RIS Human Reliability and Human Performance Database, Rev. 1 9.0 03/06/2017 This revision of RIS 2017-01 will supersede the information contained in existing RIS 2017-01. It is intended to inform licensees about the NRCs Scenario, Authoring, Characterization, and Debriefing Application software for operator simulator training and might solicit licensees, on a voluntary basis, to use the software.
MF9405 RIS NRC Staff Position on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls 8.0 03/22/2017 Program Tests This RIS will supersede the guidance provided in RIS 2012-10.
Summary Report of Open Generic Communication Projects (As Of 12/31/2017)
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 MF9464 RIS Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, 8.0 03/27/2017 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.
MF9558 RIS Clarification of Visual Examination Requirements for Reactor Upper Heads to Detect Signs of 8.0 04/05/2017 Leakage This RIS is intended to clarify the requirements for bare metal visual examination.
MF9830 RIS Common Violations of the 10 CFR Part 37 Requirements and Related Guidance Documents 5.0 06/12/2017 This RIS is being developed to inform addressees of common violations that the NRC has identified during inspections conducted to verify compliance with the requirements of 10 CFR Part 37 in order to raise awareness of these particular violations and reduce their occurrence, and to provide an overview of the difference between Part 37 and the series of security orders issued prior to the promulgation of Part 37.
MF9974 BL Degradation of Anchor Darling Double Disc Gate Valve Stem to Disc Connection 4.0 07/20/2017 This Bulletin is intended to request information regarding Anchor/Darling double disc gate valves in light of recent operating experience that involved degradation of these valves.
MG0020 IN Boiling-Water Reactor Dryout Indications Occurring During Normal Operation 4.0 07/28/2017 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.
MG0051 IN Noble Fission Gas Release During Spent Fuel Cask Loading Operations 4.0 08/04/2017 This IN is intended to inform the addressees of operating experiences related to noble fission gas releases during spent fuel loading operations.
MG0146 RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation 3.0 08/24/2017 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.
MG0173 IN Failure of Operators to Trip Plant When Experiencing Unstable Conditions 3.0 08/29/2017 This IN is intended to inform addressees of several reactor events where operators failed to place the plant in a stable, shutdown condition in a timely manner despite indications that the reactor was not in a stable condition.
Summary Report of Open Generic Communication Projects (As Of 12/31/2017)
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 MG0257 IN Operating Experience Regarding Failure to Meet Technical Specifications Requirements 2.0 09/21/2017 This IN informs addresees of several reactor events where operators failed to ensure that requirements of the plant technical specifications were met as plant conditions changed.
L2017-CRS- IN Supplier Oversight Issues Identified During NRC Vendor Inspections 2.0 10/02/2017 0062 This IN is intended to make addressees aware of recent experiences related inadequate oversight of suppliers that provide basic components to NRC-licensed facilities.
L2017-CRS- RIS Reporting Requirements for Components Exported Under General License Provisions 2.0 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.
L2017-CRS- IN Testing and Operation-Induced Degradation of 3-Stage Target Rock Safety Relief Valves 2.0 10/09/2017 0058 This IN is intended to make addressees aware of recent operating experiences related to Model 0867F 3-stage Target Rock safety relief valves (SRV). Operating experience has shown that limited flow testing of these valves can result in damage to internal valve components.
L2017-CRS- IN Process Assumptions Resulting in Unanalyzed and Improperly Analyzed Conditions Related to Long- 0.5 11/15/2017 064 Term Fissionable material Accumulation in Fuel Cycle Facilities This IN is intended to inform addressees of potential safety concerns that have been contributors to several recent safety-significant events regarding analyzed conditions related to long-term fissionable material accumulation in fuel cycle facilities.
L2017-CRS- IN Pump/Turbine Bearing Oil Sight Glass Problems .5 12/01/2017 0065 This IN will highlight recent operating experience issues involving bearing oil sight classes and resulting in damaged pump or turbine bearings.
L2017-CRS- RIS Laps of Appropriations, NRC Shutdown Due to Lapse of Funds .2 12/11/2017 0066 In the event of an NRC shutdown due to a lapse of appropriations, this RIS will inform addressees of the essential functions that will remain in place at the NRC and how to communicate with the NRC during the shutdown period.
Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND
SUMMARY
Date Opened Date Closed MG0234 RIS Process for Scheduling and Allocating Resources in Fiscal Year 2020 for 09/13/2017 12/26/2017 the Review of New Licensing Applications for Light-Water Reactors and Non-Light-Water Reactors This RIS was issued as RIS 2017-08 on December 21, 2017.