10 CFR 21.3# QUERYef07e3c8c83023aae81dd1fdff3cb78d

GO2-17-156, Transmittal of 10 CFR 21.21 (d)(4) Notification, GE-Hitachi Relays HMA124A2
ULNRC-06340, Operating Quality Assurance Manual Revision 32 Correction
ULNRC-06327, Operating Quality Assurance Manual (Oqam) Revision 32
Information Notice 2016-01, Recent Issues Related to the Commercial Grade Dedication of Allen Bradley 700-RTC Relays
Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components
Information Notice 2007-40, Inadequate Implementation of 10 CFR Part 21 Requirements by Vendors Who Supply Basic Components to Nuclear Power Plant Licensees
ULNRC-06254, Operating Quality Assurance Manual (Oqam) Revision 31, Oqam Change Notice 15-002
L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information
ULNRC-06177, Callaway Nuclear Plant - Operating Quality Assurance Manual, Rev. 031
ULNRC-06177, Callaway Nuclear Plant - Operating Quality Assurance Manual, Rev. 030c
ULNRC-06051, Callaway, Unit 1, Attachment 2 to ULNRC-06051, Operating Quality Assurance Manual (Oqam), Revision 30
ULNRC-05615, Operating Quality Assurance Manual (Oqam), Rev. 026
ULNRC-05615, Callaway - Operating Quality Assurance Manual (Oqam), Rev. 027
ULNRC-05473, Operating Quality Assurance Manual (Oqam), Revision 26
RIS 2018-05, Supplier Oversight Issues Identified During Recent NRC Vendor Inspections
SECY-19-0084, Enclosure - List of Lessons Learned Items Included in the Scope of the Regulatory Basis for Aligning Licensing Processes and Lessons Learned from New Reactor Licensing
ASLBP 10-899-02-ML-BD01, Official Exhibit - Mandatory Hearing - NRC000114-MA-BD01 - Materials License Amendment 45 to Louisiana Energy Services, L.L.C., License SNM-2010
NL-04-2459, 10 CFR 21 Report, Electric Power Research Institute Motor Operated Valve Performance Prediction Methodology Versions 1.0 Through 3.2
RS-03-051, Additional Information Supporting Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit
DD-87-14, Informs That Time Provided within Which Commission May Act to Review Director'S Decision DD-87-14 Expired.Commission Declined Review.Decision Became Final Agency Action on 870915.Served on 870925
0CAN068902, Responds to Violation Noted in Insp Repts 50-313/89-16 & 50-368/89-16.Violation Denied.Util Correctly Procured Okonite T-95 Tape as Commercial Grade & Appropriately Dedicated for safety-related Applications at Facility
BECO-87-090, Part 21 & Deficiency Rept Re Loose &/Or Missing Bolts in Hydraulic Control Unit (HCU) Support Frames of CRD Sys. Initially Reported on 870529.HCU Will Be Restored to Original Design & Bolts Inspected
BECO-87-014, Part 21 Rept Re Potential Failure of Standby Gas Treatment Sys (SGTS) Humidity Control Subsystem.Initially Reported on 870123.Caused by Bechtel Corp Design Error.Sys Will Be Verified as Operable Prior to Conducting Operations
BECO-91-096, Part 21 Rept Re Trip Latch Roller Interference on GE AK-50 Type Breakers Resulting in Failure of Automatic Transfer Scheme.Initially Reported on 910724.Breakers Modified to Prevent Clevis Pin Interference.Ge Notification Encl
W3P89-0070, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-382/89-02.Corrective Action:Maint Procedure MD-1-014, Conduct of Maint, Will Be Revised to Address Use of Nuclear Drawings
W3P88-0015, Forwards Info Re Receipt Insp & Internal Control Procedures for Fasteners & Results of Independent Testing of Fasteners in Response to NRC Compliance Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable..
DCL-24-056, Part 21 Interim Report Re Emergency Diesel Generator Fuel Snubber Valve Assembly
NEI 14-09, Guidelines for Implementation of 10 CFR Part 21 Reporting of Defects and Noncompliance
VPN-008-202, Portland General Electric Company Revision 31 to PGE-8010, Trojan ISFSI Quality Assurance Program
05000412/LER-1989-006, :on 890116,component Cooling Pump C Exhibited Sudden Loss of Flow & Immediately Secured.Caused by Expansion Joint Liner/Weld Failure,Allowing Liner to Be Drawn Into Pump Impeller.Part 21 Related
BECO-87-078, Informs That Util Reviewed Current Overall Work Plans for Emergency Preparedness,Per & Requests Removal of Date of 870812 from Tentative Schedule for Exercise at Plant
05000412/LER-1988-015-01, :on 880928,util Informed of Cracking & Spalling at Support Pads of Diesel Generator Exhaust Silencers 2EDG*SIL3A & 3B.Caused by Bent Anchor Bolts.Increased Surveillance Recommended.Part 21 Related
05000412/LER-1988-008-01, :Since Jul 1987,five Failures of Brown Boveri Ite 51 Overcurrent Relays Experienced.Caused by Short Circuiting of Output Silicon Control Rectifier Due to Impurities.Problem Also Reportable Per 10CFR21
05000321/LER-1991-015-01, :on 910823,loss of Power to B Reactor Protection Sys (RPS) Bus Due to B RPS motor-generator Set Tripped.Caused by Component Failure & MSL RM Design Inadequacy.Defective Light Bulb Replaced
LD-96-045, Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology
RIS 2015-08, Oversight of Counterfeit, Fraudulent, and Suspect Items in the Nuclear Industry