Thermal Overload Protection for Electric Motors on Motor-Operated Valves
Regulatory Guide 1.106# QUERY5e0ca962ea609282d8326a1f5b02b053
Regulatory Guide 1.106# QUERY4f7ede7d70236219e778ec0d4bb868f5
Regulatory Guide 1.106# QUERY2f424dc36dc53148ebe16fe2b866f7dd
Regulatory Guide 1.106# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9

Regulatory Guide 1.106# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
Regulatory Guide 1.106# ERR1dd423a8697e32d6813ecd1a7aae482c
RA-20-0012, License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices
NL-17-0534, Technical Requirements Manual
W3F1-2016-0040, Technical Requirements Manual Update to the NRC
Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire
PLA-3642, Forwards Rev 44 to Fsar.Rev Submitted as Result of Commitments Contained in Util to Revise FSAR to Reflect Design of Isolation for Class 1E Circuits from non-Class 1E Circuits
NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program
HNP-15-046, Transmittal of Technical Specifications Bases
SBK-L-14231, Submittal of Changes to Technical Specification Bases
GNRO-2014/00057, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
RS-14-006, Updated Safety Analysis Report, Revision 16, CPS Operational Requirements Manual
RS-13-009, Operational Requirements Manual (Orm) 2013
HNP-12-130, Transmittal of Technical Specifications Bases
SBK-L-12052, Submittal of Changes to Technical Specification Bases
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Requirements Manual
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figure 7.6.5-1 (Sheet 1 of 2) Through Figure 8.3.1-1 (Sheet 4 of 34)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
ULNRC-06410, Callaway Plant, Unit 1 - Response to Request for Additional Information Concerning Proposed Revision of FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (Ldcn 16-0001)
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 8.0 - Electric Power
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 8.0 - Electric Power
LR-N08-0168, License Amendment Request - Action for Inoperable Inverters
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety Features
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
SECY-04-0233, Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire
L-2006-264, Technical Specification Bases Control Program Periodic Record of Bases Changes TS 6.8.4.j.4
NL-18-1299, Technical Requirements Manual
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
LR-N05-0030, Request for Change to Technical Specifications Relocation of Overcurrent Protective Devices
GO2-00-038, Independent Spent Fuel Storage Installation 2004 Annual Operating Report
RAIO-0318-59292, LLC - Response to NRC Request for Additional Information No. 354 (Erai No. 9359) on the NuScale Design Certification Application
SBK-L-20001, License Amendment Request 19-03, Application to Revise Degraded Voltage Time Delay Setpoint
SBK-L-04121, Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-04050, Submittal of Changes to the Plant Technical Specification Bases
L-2003-291, Technical Specification Bases Control Program, Periodic Report of Bases Changes, TS 6.8.4.j.4
W3F1-2003-0031, Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments
NL-20-0442, Revisions to Technical Requirements Manual (TRM)
SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request
LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
IA-85-187, Partially Withheld Anonymous Allegation Re Proposed Enforcement Action - Grand Gulf Nuclear Station
PLA-2736, Forwards Response to IE Bulletin 85-003 Re motor-operated Valves,Per 860829 request.Motor-operated Valves in HPCI & RCIC Sys Requiring Testing for Operational Readiness Listed
JAFP-86-0833, Forwards Suppl to Response to IE Bulletin 85-003, Motor- Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Per 860729 Request.Util Waiting for Sept 1986 BWR Owners Group Rept Re Valves
B12311, Forwards Review for Isap Topic 1.10, Torque Switch Mods, Per SEP Topic III-10.A.Torque Switch & Thermal Overload Protection Issues Adequately Addressed.Further Evaluation Ongoing
RBG-36803, Responds to NRC Re Violations Noted in Insp Rept 50-458/92-04.Corrective Actions:Test Procedure Developed
B12931, Proposed Tech Specs Re Electrical Power Sys
L-85-439, Responds to NRC Re Violations Noted in Insp Repts 50-250/85-32 & 50-251/85-32.Corrective Actions:Maint Procedures,Controls Over Plant Work Orders Training & Experience of Maint Personnel Will Be Augmented
B11638, Forwards Reviews of Integrated Safety Assessment Program Topics,Including 1.01 Re Gas Turbine Generator Start Logic mods,1.04 Re Reactor Water Cleanup Sys Pressure Interlock, 1.05 Re Ventilation Sys & 1.15 Re FSAR Update
RBG-21773, Forwards Proposed Revs to Tech Specs,For Review.Changes Consist of Comments & Typos Noted in Review of 850724 Final Draft
ST-HL-AE-1882, Forwards Draft Rev 2 to Tech Specs Identified for Further Comment or Resolution During NRC 870107 Site Visit. Justifications Also Encl
SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
ST-HL-AE-1590, Forwards Response to Draft SER Item 78,NRC Question 430.21 Re Electrical Penetration Protection.Item Should Be Considered closed.W/38 Oversize Penetration Coordination Curves
ET-NRC-93-3815, Forwards Responses to Requests for Addl Info on AP600 from NRC Ltrs Dtd 921009,14 & 1116
RC-96-0168, Submits Suppl Info,As Requested by NRC to Support SE Presented as Attachment II to Util ,Requesting Amend to TS Re MOVs Thermal Overload Protection & Bypass Devices
HL-2229, Responds to NRC Re Violations Noted in Insp Repts 50-321/92-08 & 50-366/92-08.Corrective Actions:Design Change Request 92-075 Implemented to Install Jumpers Around Thermal Overload Devices of 12 Unit 1 motor-operated Valves
HL-2074, Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept, 1991
RBG-19294, Forwards Responses to All Deficiencies,Unresolved Items & Details A2.8-1 & A3.3-1,per Integrated Design Insp Rept 50-458/84-18 on 840409-0601.Limited Design Review to Be Conducted by Util,Per NRC
B11111, Forwards Response to Draft SER Open Items
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
JSP-078-92, Application for Amend to License NPF-62,changing TSs to Delete Component Lists,As Recommended in Generic Ltr 91-08 & Deleting Reactor Vessel Specimen Withdrawal Schedule,As Recommended by Generic Ltr 91-01
PLA-4181, Forwards Description of Rev 47 Changes to FSAR for Sses.Most Current Rev of Design Drawings Incorporated in Rev 47 to Fsar.Fsar Encl
TXX-4901, Forwards Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Per 860430 Request for 2 Month Extension to Response Deadline
PY-CEI-NRR-0299, Requests Exception to Svc Discharge Test Requirements of Reg Guide 1.129/IEEE 450-1980,per Util .Svc Test Will Be Performed Every 18 Months Unless Test Coincides W/Battery Discharge Test.Proposed FSAR Text Encl
LD-92-078, Submits Supplemental Info for Previous Sys 80+ Rais, Including Response to TMI Item II.E.3.1 Which Confirms That Backup Pressurizer Heaters Are Not Relied Upon or Required for Natural Circulation in RCS
L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements
Information Notice 2006-26, Failure of Magnesium Rotors in Motor-Operated Valve Actuators
05000373/LER-1996-022-03, :on 961213,determined That Thermal Overload Protection Devices for RHR Valves Were Not Bypassed.Caused Indeterminate.Implemented Design Changes to Revise Thermal Overload Bypass Circuit
05000416/LER-1984-055, :on 841130,discrepancies Identified Between Design & Commitments to Reg Guide 1.63 Involving Overcurrent Protection of Containment Penetrations
LD-91-067, Forwards Response to NRC 910729 Request for Addl Info Re Engineering SSAR - Design Certification Covering IEEE Stds, Offsite Power Sys,Control Room Indication of Emergency Diesel Generator Operational Status & Dc Power Sys
05000373/LER-1983-155-03, /03L-0:on 831229,util Informed by Sargent & Lundy That Engineering Change Notice Forthcoming Re Overload Bypass Circuit Design on RHR Min Flow Bypass Valves.Mod Immediately Implemented & Completed on 831230
B10450, Submits Addl Info Re Electrical Protection of Motor Operated Valves,In Response to NRC Evaluations of SEP Topic III-10.A, Thermal Overload Protection for Motors of Motor Operated Valves.Ieee Article Encl
05000254/LER-1990-004-04, :on 900310,reactor Scram Occurred Due to Turbine Generator Load Mismatch.Caused by Failure of Negative Sequence Time Overcurrent Relay.Relay Repaired
AECM-80-225, Forwards Response to NRC Questions 031.56,031.71 & Revised Responses to Questions 031.38,031.54,031.60 & 031.75. Responses Will Be Incorporated Into Oct 1980 Amend to FSAR
TXX-8980, Forwards Changes to Be Included in Future FSAR Amend Re Electrical Separation Between Class 1E Power Conduits & non-class 1E Instrument Control Cable Tray & Cable.Change Will Be Evaluated Under 10CFR50.59 Procedures
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
RAIO-1117-57010, LLC Supplemental Response to NRC Request for Additional Information No. 27 (Erai No. 8788) on the NuScale Design Certification Application
L-90-110, Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question
GO2-91-167, Responds to NRC Re Violations Noted in Insp Rept 50-397/91-16.Corrective Actions:Improvement Initiatives Have Been Planned to Strengthen Mgt Oversight & Implementation of MOV Program
GO2-86-081, Application for Amend to License NPF-21,changing Tech Specs to Add Auxiliary Steam & Fuel Pool Cooling Sys Valves to Update Table 3.8.4.3-1 Re Motor Operated Valves Thermal Overload Protection.Fee Paid
RAIO-0917-56203, LLC Response to NRC Request for Additional Information No. 147 (Erai No. 9041) on the NuScale Design Certification Application
ULNRC-06331, Proposed Revision of Callaways FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001)
ULNRC-06182, Response to NRC Regulatory Issue Summary (RIS) 2014-13, Planned Licensing Action Submittal for All Power Reactor Licensees
RIS 2005-30, Clarification of Post-Fire Safe-Shutdown Circuit Regulatory Requirements
LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
NUREG-1296, Thermal Overload Protection for Electric Motors on Safety-Related motor-Operated Valves - Generic Issue II.E.6.1
AECM-88-0186, Application for Amend to License NPF-29,changing Tech Specs to Add Alternate DHR Sys.Fee Paid
TSTF-21-02, Submittal for Information of TSTF-GG-21-01, Technical Requirements Manual and Operational References (TRM) Format and Content Guideline