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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML18302A097  + (Clarification Email on RAI 28 Response for MRP-227, Revision 1)
• ML090370786  + (Clarification Following Phone Call on Need for Supplemental Information During Acceptance Review from Containment and Ventilation Branch)
• ML18094A724  + (Clarification Language for FLEX 3-28-18 for NUMARC 93-01 Rev 4E)
• ML073240244  + (Clarification Letter for Gothic)
• PMNS20241419, Clarification Meeting on Applicability Requirements for RG 1.13 and SRPs 9.1.2 & 9.1.4 to Water Levels During Refueling Operations  + (Clarification Meeting on Applicability Requirements for RG 1.13 and SRPs 9.1.2 & 9.1.4 to Water Levels During Refueling Operations)
• ML091820102  + (Clarification Needed on MPS2 SG Tube Inspection Report)
• ML091810677  + (Clarification Needed on MPS3 ISI Intervak RR No. IR-3-08)
• ML21141A151  + (Clarification Needs-Westinghouse Lr EIS-WEC Response)
• RIS 2007-01, Clarification Of NRC Guidance For Maintaining a Standard Emergency Action Level (EAL) Scheme  + (Clarification Of NRC Guidance For Maintaining a Standard Emergency Action Level (EAL) Scheme)
• ML15356A779  + (Clarification Pertaining to Submittals 15-245 and 15-245A as Discussed in November 30, 2015 Teleconference)
• ML110601208  + (Clarification Question Regarding the Response to RAI 3.1.2.3-01 in Columbia Letter Dated September 21, 2010)
• ML102150328  + (Clarification Question for Shearon Harris RR 13R-07 - Shearon Harris RAIs for RR 13R-07)
• ML22265A131  + (Clarification Questions in Regard to Holtecs Responses to RAIs for the Shielding Topical Report)
• ML24289A186  + (Clarification Questions on Fort Calhoun Station Phase 1 Final Status Survey Report Request for Additional Information Responses)
• ML102080268  + (Clarification RAI DPC LAR in Support of Dry Cask Storage Project at LACBWR)
• ML22125A012  + (Clarification RAI Partial Response Email from C Smith to a Snyder)
• RS-13-208, Clarification Re Inservice Testing of High Pressure Coolant Injection Valves 2(3)-2301-32-SO  + (Clarification Re Inservice Testing of High Pressure Coolant Injection Valves 2(3)-2301-32-SO)
• ML20212D072  + (Clarification Re Numerous Employees Memorandum of Law.* Discusses Numerous Employees 870123 Position That Surveillance & Administrative Procedures Were Not Legal Requirements.Certificate of Svc Encl.Related Correspondence)
• ML19294A357  + (Clarification Re Provisions of Reg Guide 1.130 of July 1977 Are Offered)
• ULNRC-05620, Clarification Regarding Application of ASME Code Relief Request Approved for Callaway  + (Clarification Regarding Application of ASME Code Relief Request Approved for Callaway)
• ML24267A055  + (Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395))
• ML24267A064  + (Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395))
• ML24267A054  + (Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395))
• ML24267A059  + (Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395))
• ML24221A211  + (Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395))

• RS-06-107, Clarification Regarding Backup Stability Protection Methodology  + (Clarification Regarding Backup Stability Protection Methodology)

• ML060680239  + (Clarification Regarding Commitment Associated with License Amendment Request for Extension of Diesel Generator Completion Time)
• ML031270454  + (Clarification Regarding Emergency Feedwater Safety Evaluation Dated June 11, 2002 Oconee UFSAR Section 10.4.7)
• HBL-21-017, Clarification Regarding Final Status Survey Report for Humboldt Bay Power Plant  + (Clarification Regarding Final Status Survey Report for Humboldt Bay Power Plant)
• ML092290359  + (Clarification Regarding H* Parc)
• SBK-L-09204, Clarification Regarding How Information in WCAP-17071-P, H*: Alternate Repair Criteria for Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Meets Considerations of 10 CFR 2.390(b)  + (Clarification Regarding How Information in WCAP-17071-P, H*: Alternate Repair Criteria for Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Meets Considerations of 10 CFR 2.390(b))
• NLS2002063, Clarification Regarding Inspections and Reports for Core Spray Sparger Piping for Cooper Nuclear Station  + (Clarification Regarding Inspections and Reports for Core Spray Sparger Piping for Cooper Nuclear Station)
• RS-09-155, Clarification Regarding License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time  + (Clarification Regarding License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time)
• L-2003-260, Clarification Regarding NDE Examinations for the Risk Informed Inservice Inspection Relief Request  + (Clarification Regarding NDE Examinations for the Risk Informed Inservice Inspection Relief Request)
• ML033040149  + (Clarification Regarding Relief Request Concerning risk-informed Inservice Inspection)
• ML023520168  + (Clarification Regarding Request for Additional Information to 60-Day Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity)
• L-12-351, Clarification Regarding Response to Request for Additional Information Related to Request for Alternative Examination Requirements for American Society of Mechanical Engineers (ASME) Class 1 Piping Welds  + (Clarification Regarding Response to Request for Additional Information Related to Request for Alternative Examination Requirements for American Society of Mechanical Engineers (ASME) Class 1 Piping Welds)
• ML060660387  + (Clarification Regarding Use of Supplemental Responders and Commitment to Incorporate Number of Supplemental Responders in the Security Plan)
• GO2-06-029, Clarification Regarding a Commitment Associated with the License Amendment Request for Extension of Diesel Generator Completion Time  + (Clarification Regarding a Commitment Associated with the License Amendment Request for Extension of Diesel Generator Completion Time)
• ML23352A196  + (Clarification Regarding the Accepted Versions of Nedc 33376P, Revision 4, LANCR02 Lattice Physics Model Description, NEDC-33377P, Revision 4, LANCR02 Lattice Physics Model Qualification Report, and NEDC-33935P, Revision 0, LANCR02/PANAC11 a)
• RS-13-219, Clarification Regarding the Inservice Testing of Dresden Nuclear Power Station High Pressure Coolant Injection (HPCI) Valves 2(3)-2301-32-SO  + (Clarification Regarding the Inservice Testing of Dresden Nuclear Power Station High Pressure Coolant Injection (HPCI) Valves 2(3)-2301-32-SO)
• ML100470320  + (Clarification Regarding the Number of Tritium Producing Burnable Absorber Rods in Operating Cycle 10 and Program Update)
• RS-13-164, Clarification Regarding the Testing Frequency for Fifth Inservice Testing Interval Relief Request RV-23H  + (Clarification Regarding the Testing Frequency for Fifth Inservice Testing Interval Relief Request RV-23H)
• NLS2002018, Clarification Related to NRC Inspection Report 50-298/0112  + (Clarification Related to NRC Inspection Report 50-298/0112)
• L-06-011, Clarification Related to the Firstenergy Nuclear Operating Company Request for Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor  + (Clarification Related to the Firstenergy Nuclear Operating Company Request for Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor)
• ML102440139  + (Clarification Requested (Ihpb) Extended Power Uprate License Amendment Request)
• ML24289A204  + (Clarification Responses)
• ML25133A100  + (Clarification Restart Memo)
• ML19199A419  + (Clarification Warranted to Ensure Orderly Administration of Industrial Security Plan & Aircraft Hazard Analysis Review)
• ML24199A001  + (Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2))
• ML23194A044  + (Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan)