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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 


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.
 
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.}}

Latest revision as of 21:19, 20 October 2019

Summary Report of Open Generic Communication Projects (as of 06/30/2018)
ML18183A443
Person / Time
Issue date: 07/02/2018
From:
Office of Nuclear Reactor Regulation
To:
Lee E
References
Download: ML18183A443 (4)


Text

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.