ML18032A166
| ML18032A166 | |
| Person / Time | |
|---|---|
| Issue date: | 02/01/2018 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML18032A166 (5) | |
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Summary Report of Open Generic Communication Projects (As Of 01/31/2018)
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 MF3949 RIS RIS 2005-29 Rev 1 Anticipated Transients That Could Develop into More Serious Events 45.0 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 43.0 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 35.0 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 24.0 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 14.0 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 10.0 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 9.0 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 01/31/2018)
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 MF9464 RIS Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, 9.0 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 9.0 04/05/2017 Leakage This RIS is intended to clarify the requirements for bare metal visual examination.
MF9974 BL Degradation of Anchor Darling Double Disc Gate Valve Stem to Disc Connection 5.0 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 5.0 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 5.0 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 4.0 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 4.0 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.
MG0257 IN Operating Experience Regarding Failure to Meet Technical Specifications Requirements 3.0 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 3.0 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.
Summary Report of Open Generic Communication Projects (As Of 01/31/2018)
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 L2017-CRS- RIS Reporting Requirements for Components Exported Under General License Provisions 3.0 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 3.0 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- 1.5 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 1.5 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 1.2 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.
L2018-CRS- IN Inadequate Management Measures for Process Isolation Controls Designated as Items Relied on for .2 01/19/2018 XXXX Safety This IN will inform addressees of recent issues and inspection findings regarding programs and procedures for determining and implementing management measures for isolation controls required to be available and reliable to perform specified safety functions to prevent or mitigate accident sequences.
L2018-CRS- RIS Supplier Oversight From Recent Vendor Inspections .1 01/22/2018 XXXX 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-CRS- IN Failure to Enter the Required Technical Specification Action Statement for Operation During Recent .1 01/23/2018 XXXX 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.
Summary Report of Open Generic Communication Projects (As Of 01/31/2018)
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-CRS- RIS Preparation and Scheduling of Operator Licensing Examinations .1 01/23/2018 XXXX This RIS is intended to inform addressees of the NRC staffs need for updated information on project site-specific operator licensing examination schedules and on the estimated number of applicants planning to take operator licensing examinations. This information will help the NRC plan its resources more effectively.
L2018-CRS- RIS Clarification for Reporting Transactions to the National Source Tracking System Involving .1 01/25/2018 XXXX 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.
Closed Generic Communication Projects Since Last Report Division of Inspection and Regional Support CAC/EPIDS NUMBER TITLE AND
SUMMARY
Date Opened Date Closed MF9830 RIS Common Violations of the 10 CFR Part 37 Requirements and Related 06/12/2017 01/22/2018 Guidance Documents This RIS was issued as RIS 2018-01 on January 22, 2018.