Pages that link to "L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)"
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The following pages link to L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006):
Displayed 50 items.
- L-MT-09-100, Xcel Energy Request for NRC Concurrent Review of Monticello Nuclear Generating Plant Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request (LAR) with MNGP Extended Power Uprate (EPU) LAR Review Delay (← links)
- L-MT-09-096, Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant (← links)
- L-MT-18-051, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, (← links)
- L-MT-14-042, Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request (← links)
- L-MT-10-049, Response to Request for Additional Information for the Monticello Proposed Maximum Extended Load Line Limit Analysis Plus (Mellla+) Amendment (← links)
- L-MT-09-043, Enclosure 2, NSPM Draft Response L-MT-09-043 to Mechanical and Civil Engineering Branch RAIs - Steam Dryer Proprietary Information (← links)
- L-MT-09-056, NAD-MN-020, Revision 0, Monticello Nuclear Generating Plant, MNGP Core Operating Limits Report for Cycle 25. (← links)
- L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 (← links)
- L-MT-09-007, Response to November 14, 2008, Request for Additional Information for License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Funct (← links)
- L-MT-08-064, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.21 0, for Storage of Spent Fuel (← links)
- L-MT-08-021, Commitment Closutechnical Support Center Dose Assessment in Conjunction with the Full-Scope Alternative Source Term License Amendment (← links)
- L-MT-08-025, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process (← links)
- L-HU-08-009, Guarantee of Payment of Deferred Premiums (← links)
- L-MT-06-086, Response to Request for ECCS Surveillance Documentation to Confirm the Functionality of the LPCI Loop Select Time Delay Relays During Past Surveillance Testing (← links)
- L-MT-06-040, Emergency Response Data System (ERDS) - Revision to Previously Submitted Data Point Library Information (← links)
- L-MT-06-020, Clarification to 10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval (← links)
- L-MT-06-034, Copy of Applicable Portions of the Us NRC and Monticello Improved Technical Specifications Conversion Website (← links)
- L-MT-06-029, Supplemental Information Regarding Monticello Nuclear Generating Plant License Renewal Application (← links)
- L-MT-06-019, Supplemental Information and Response to Requests for Additional Information Regarding Monticello Nuclear Generating Plant License Renewal Application (← links)
- L-MT-06-009, Revise Implementation Period for the LAR for a Selective Scope Application of an Alternative Source Term Methodology for Re-evaluation of the Fuel Handling Accident (← links)
- L-MT-06-014, Supplement to Responses to Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application (← links)
- L-MT-05-115, Response to Two Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application (← links)
- L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- L-MT-19-003, Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 (← links)
- L-MT-18-076, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-073, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee... (← links)
- L-MT-18-074, Independent Spent Fuel Storage Installation - Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1 (← links)
- L-MT-18-009, License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note (← links)
- L-MT-18-067, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-059, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-058, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ... (← links)
- L-MT-18-057, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-053, Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 (← links)
- L-MT-18-055, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-039, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel (← links)
- L-MT-18-043, Online Reference Portal for NRC Review of License Amendment Requests to Adopt TSTF-425 and 10 CFR 50.69 (← links)
- L-MT-18-041, Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel (← links)
- L-MT-18-040, Follow-up to Interim Report of a Deviation or Failure to Comply (← links)
- L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements (← links)
- L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360 (← links)
- L-MT-18-031, Project Plan Progress Update Toward Restoring 10 CFR 72 Compliance to Dry Shielded Canisters Designated 11 Through 16 (← links)
- L-MT-18-023, 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval (← links)
- L-MT-18-027, 2017 Annual Radioactive Effluent Release Report (← links)
- L-MT-18-029, 2017 Annual Radiological Environmental Operating Report (← links)
- L-MT-18-026, NRC Regulatory Issue Summary 2018-02 - Preparation and Scheduling of Operator Licensing Examinations (← links)
- L-MT-18-021, 2017 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) (← links)
- L-MT-18-020, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control (← links)
- L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- L-MT-18-001, Request for Permanent Exemption from 10 CFR 50 Appendix R III.G.2.a Requirements for Exposed Structural Steel (← links)