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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 04/30/2018)
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 supplement to RIS 2002-22 is intended to clarify the NRC's 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. This RIS is intended to clarify the requirements for bare metal visual examination.
Division of Inspection and Regional Support (Information in this report is provided for general informational purposes only and is subject to change without notice.)
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 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 maintain. This IN is intended to make addressees aware of recent experiences related inadequate oversight of suppliers that provide basic components to NRC-licensed facilities.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.
(For additional information contact Erika Lee at: erika.lee@nrc.gov)
This IN will highlight recent operating experience issues involving bearing oil sight classes and resulting in damaged pump or turbine bearings. 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 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 licensee's technical specifications. These conditions existed during quarterly surveillance testing of main steam isolation valve and turbine stop valve logic. 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.
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)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.
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. 


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. This was issued as RIS 2018-02 on March 26, 2018. This was issued as IN 2018-06 on April 10, 2018.}}
==SUMMARY==
(Mon) OPENED MF3949    RIS RIS 2005-29 Rev 1 Anticipated Transients That Could Develop into More Serious Events                                48.0  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                                                                                            46.0  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                                                                  38.0  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                                                  27.0  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                            17.0  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 MF9464    RIS Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348,                    12.0  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                          12.0  04/05/2017 Leakage This RIS is intended to clarify the requirements for bare metal visual examination.
 
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                                      8.0      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.
MG0146      RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation                    7.0      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.
L2017-CRS-  RIS Supplier Oversight Issues Identified During NRC Vendor Inspections                                            6.0      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                                6.0      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 Pump/Turbine Bearing Oil Sight Glass Problems                                                                  4.0      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.
L2018-CRS-  RIS Supplier Oversight From Recent Vendor Inspections                                                              3.0      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-CRS-  IN Failure to Enter the Required Technical Specification Action Statement for Operation During Recent              3.0      01/23/2018 0002        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.
L2018-CRS-  RIS Clarification for Reporting Transactions to the National Source Tracking System Involving                      3.0      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.
 
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-  IN Evaluations Supporting Changes to Plant Configuration                                                            1.0    03/29/2018 GEN-0001 This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC).
L-2018-  IN Duties and Responsibilities of Armed Responders                                                                  1.0    03/29/2018 GEN-0002 This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities.
L-2018-  IN Foreign Material from Installation of Thermo-Lag 770-1 Results in High Energy Arc Flash and Damage                  .1    04/19/2018 CRS-XXXX  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.
 
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 Process Assumptions Resulting in Unanalyzed and Improperly Analyzed              11/15/2017  03/26/2018 CRS-0064 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.
L2018-  RIS Preparation and Scheduling of Operator Licensing Examinations                  01/23/2018  03/26/2018 CRS-0001 This was issued as RIS 2018-02 on March 26, 2018.
L2018-  IN Inadequate Management Measures for Process Isolation Controls Designated        01/19/2018  04/10/2018 CRS-0000 as Items Relied on for Safety This was issued as IN 2018-06 on April 10, 2018.}}

Revision as of 06:12, 21 October 2019

Summary Report of Open Generic Communication Projects (as of 04/30/2018)
ML18121A130
Person / Time
Issue date: 05/01/2018
From:
Office of Nuclear Reactor Regulation
To:
Lee E
References
Download: ML18121A130 (4)
v • d • e


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 48.0 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 46.0 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 38.0 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 27.0 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 17.0 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 MF9464 RIS Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, 12.0 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 12.0 04/05/2017 Leakage This RIS is intended to clarify the requirements for bare metal visual examination.

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 8.0 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.

MG0146 RIS Electronic Signature Use for Medical Licensee Internal Documents Required by NRC Regulation 7.0 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.

L2017-CRS- RIS Supplier Oversight Issues Identified During NRC Vendor Inspections 6.0 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 6.0 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 Pump/Turbine Bearing Oil Sight Glass Problems 4.0 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.

L2018-CRS- RIS Supplier Oversight From Recent Vendor Inspections 3.0 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-CRS- IN Failure to Enter the Required Technical Specification Action Statement for Operation During Recent 3.0 01/23/2018 0002 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.

L2018-CRS- RIS Clarification for Reporting Transactions to the National Source Tracking System Involving 3.0 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.

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- IN Evaluations Supporting Changes to Plant Configuration 1.0 03/29/2018 GEN-0001 This information notice is being issued to reiterate the need for comprehensive evaluations of configuration changes to structures, systems and components (SSC).

L-2018- IN Duties and Responsibilities of Armed Responders 1.0 03/29/2018 GEN-0002 This information notice is being issued to notify addressees of incomplete documentation regarding armed responder duties and responsibilities.

L-2018- IN Foreign Material from Installation of Thermo-Lag 770-1 Results in High Energy Arc Flash and Damage .1 04/19/2018 CRS-XXXX 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.

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 Process Assumptions Resulting in Unanalyzed and Improperly Analyzed 11/15/2017 03/26/2018 CRS-0064 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.

L2018- RIS Preparation and Scheduling of Operator Licensing Examinations 01/23/2018 03/26/2018 CRS-0001 This was issued as RIS 2018-02 on March 26, 2018.

L2018- IN Inadequate Management Measures for Process Isolation Controls Designated 01/19/2018 04/10/2018 CRS-0000 as Items Relied on for Safety This was issued as IN 2018-06 on April 10, 2018.

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