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RIS 2007-06, Regulatory Guide 1.200 Implementation
Information Notice 2006-18, Significant Loss of Safety-related Electrical Power at Forsmark, Unit 1, in Sweden
RIS 2009-11, Withdrawn NRC Regulatory Issue Summary 2009-11: Preparation and Scheduling of Operator Licensing Examinations
TSTF-07-19, Response to NRC Request for Additional Information (RAI) Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated February 28, 2007
TSTF-07-14, TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions
BVY 07-039, Core Operating Limits Report for Cycle 26
NL-07-0117, Technical Specifications Amendment Request Engineered Safety Feature Room Coolers
NL-07-0731, Application for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency
NOC-AE-07002156, Proposed Change to Surveillance Requirement 4.5.2.d
CNRO-2007-00023, Proposed License Transfer and Conforming License Amendment in the Matter of Entergy Gulf States, Inc
NG-07-0412, Response to Request for Additional Information Regarding License Amendment Request (Tscr - 056A): Elimination of License Condition 2.C.(2)(b) for Performance of Large Transient Tests for Extended Power Uprate
NOC-AE-07002168, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)
RC-07-0085, Virgil Summer - Request to Use Alternatives to ASME Code Section XI Requirements for Application of Weld Overlay Repairs (RR-III-05)
RC-07-0081, ECCS Evaluation Model Revisions Annual Report
W3F1-2007-0026, Submittal of Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models
RC-07-0084, (Vcsns), Request for Burnup Extension of Exemption Request
L-07-073, Supplement to Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements (Request No. BV1-PZR-01, Revision 1)
L-2007-082, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2006 Annual Report
SBK-L-07088, Steam Generator Inservice Inspection
W3F1-2007-0027, Response to NRC Questions Regarding Acceptability of Degraded Batwings
NL-07-066, Reactor Vessel Upper Head Inspection Results; Spring 2007 Refueling Outage (3R14)
NL-07-067, Submittal of Reactor Vessel Lower Head Inspection Results for Spring 2007 Refueling Outage
ULNRC-05401, Transmittal of 2006 Annual Radioactive Effluent Release Report
NG-07-0368, Relief Request for 3rd Period Limited Weld Examinations
NL-07-1082, Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests
3F0307-08, License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process
RC-07-0082, Assessment of Feasibility for Leak Detection Enhancement (CR-07-00439)
LR-N07-0123, Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate
CPSES-200700738, License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves
PLA-6210, Extended Power Uprate Application Vessels and Internals Integrity Technical Review Request for Additional Information Responses
NRC-07-0029, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator
NOC-AE-07002113, Proposed Change to Technical Specification 3.7.1.2, Auxiliary Feedwater System.
PLA-6198, Proposed License Amendments 285 and 253, Extended Power Uprate Application Balance-of-Plant Safety Systems Request for Additional Information Responses
CNRO-2007-00022, Request for Alternative GG-ISI-002, Response to Requests for Additional Information
L-MT-07-034, Response to Request for Additional Information to Revise TS Surveillance Requirement 3.5.1.3 to Correct the Alternate Nitrogen System Pressure
L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication
NOC-AE-07002152, Response to NRC Request for Additional Information, Supplement to Revised Broad Scope Risk-Informed Technical Specification Amendment Request
GNRO-2007/00034, Report of 10 CFR50.59 Safety Evaluations and Commitment Changes - April 1, 2006 Through March 31, 2007
NG-07-0367, Relief Request for Drywell Stabilizer Examinations
SVP-07-031, Core Operating Limits Report for Quad Cities Unit 1 Cycle 20
JAFP-07-0067, License Renewal Application, Amendment 11
1CAN050704, Unit 1, Entergy Actions to Address Once Through Steam Generator Degradation
BSEP 07-0037, Annual Radiological Environmental Operating Report for 2006
HNP-07-041, Inservice Inspection Relief Request 1, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
PLA-6195, Extended Power Uprate Application Electrical Engineering Technical Review Request for Additional Information Responses
PLA-6194, Proposed License Amendments 285 and 253, Extended Power Uprate Application Health Physics Technical Review, Request for Additional Information Responses
LR-N07-0105, Report of Changes, Tests and Experiments for May 13, 2005 Through May 1, 2007
LR-N07-0086, Response to Request for Additional Information for License Amendment - Topical Report References in Technical Specification 6.9.1.9, Core Operating Limits Report
HNP-07-073, Withdrawal of the Relief Request from ASME Code Inservice Testing Requirements for the Second 10-Year Interval
BSEP 07-0034, Core Operating Limits Report, Revision 1 for Unit 1 Cycle 16
NL-07-060, Revised Core Operating Limits Report
PLA-6182, Annual Radiological Environmental Operating Report for Calendar Year 2006 in Accordance with Technical Specification 5.6.2
PLA-6206, Response to NRC GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients, PLA-6206
L-HU-07-016, Revision to Correspondence Service Lists for Nuclear Management Company, LLC
NLS2007028, Annual Radiological Environmental Report for the Period January 1, 2006 Through December 31, 2006
BVY 07-038, Submittal of 2006 Annual Radiological Environmental Operating Report
RS-07-084, Response to Request for Additional Information Regarding Relief Request 14R-16
BVY 07-037, Annual 2006 Radioactive Effluent Release Report
SVP-07-029, Annual Radiological Environmental Operating Report for 2006
LIC-07-0046, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
L-PI-07-037, 10 CFR 50.55a Request 1-RR-4-6 for the Prairie Island, Unit 1, Fourth Ten-year Interval Inservice Inspection Program
2CAN050702, License Amendment Requesting, Technical Specification 3.1.1.4, Moderator Temperature Coefficient
L-2007-053, Annual Radiological Environmental Operating Report
L-2007-039, License Amendment Request (LAR 190), Administrative Changes to Technical Specification 6.2.1.a and 6.8.1.a
LR-N07-0094, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
SCH07-057, New Jersey Pollutant Discharge Elimination System Discharge Monitoring Report
CPSES-200700915, Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability
BSEP 07-0040, NRC Correspondence Distribution List Update
BSEP-07-0035, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
HNP-06-089, Response to Request for Additional Information Regarding License Amendment Request to Revise Values Associated with the Steam Generator Water Level (SGWL) Trip Setpoints
PLA-6191, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Piping and Nondestructive Examination Technical Review Request for Additional Information Responses
PLA-6199, Resubmittal of Proprietary Information
L-PI-07-035, 2006 Annual Radiological Environmental Monitoring Program (REMP) Report
ULNRC-05415, Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
NL-07-055, Response to Generic Letter 2007-01
LR-N07-0095, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
L-2007-076, Steam Generator Tube Inservice Inspection Special Report
LR-N07-0098, Summary of Revised Regulatory Commitments
LR-N07-0103, Units 1 & 2, Correction to Technical Specification Pages/Amendment 276 and 258
RNP-RA/07-0045, Radiological Environmental Operating Report for the Period of January 1, 2006 Through December 31, 2006
NOC-AE-07002163, Response to Request for Additional Information on Risk-Informed Technical Specification Amendment Request
RNP-RA/07-0018, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
RS-07-083, Request to Extend the First Period of the Fourth 10-Year Inservice Inspection Interval for Twenty Reactor Pressure Vessel Welds
RS-07-060, Supplemental Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.
RBG-46691, Radioactive Effluent Release Report for 2006
NLS2007040, Affidavit Requesting Withholding from Public Disclosure Regarding Response to Request for Additional Information to Support NRC Review of License Amendment Request to Increase Capacity of Onsite Spent Fuel Storage at Cooper
L-HU-07-015, Revision to Correspondence Service Lists for Nuclear Management Company, LLC
SVP-07-027, 90-Day Post Outage ISI Letter, Dated July 14, 2006
L-PI-07-039, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time
HNP-07-067, 90-Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
RS-07-079, Plant Specific ECCS Evaluation Change - 10 CFR 50.46 Report
LR-N07-0076, 2007 Annual Report - Guarantees of Payment of Deferred Premiums
NRC-07-0017, Detroit Edison'S 90-Day Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigations Systems or Cause Plant Transients.
NLS2007029, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
ULNRC-05411, Transmittal of Callaway, Cycle 16, Core Operating Limits Report, Revision 0
JAFP-07-0059, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transient.
GO2-07-079, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
PLA-6176, Unit 2, Responses to the Request for Additional Information Transmitted to PPL Extended Power Update Application Regarding Steam Dryer and Flow Effects
NL-07-1001, Unit 2, Pressurizer Surge Nozzle Full Structural Weld Overlay Nondestructive Examination Results - Spring 2007 Outage (2R18)
L-2007-079, License Amendment Request No. 178: Spent Fuel Pool Boraflex Remedy, Response to NRC Request for Additional Information
L-07-055, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
L-2007-067, Plants, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
LR-N07-0099, Response to Request for Additional Information Request for License Amendment, Extended Power Uprate
BVY 07-034, License Renewal Application Annual Update
NL-07-0987, Fourth Interval Inspection (ISI) Plan Correction
PLA-6183, Transmittal of Radioactive Effluent Release Report and Offsite Dose Calculation Manual
L-PI-07-044, Response to NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program
W3F1-2007-0017, Ninety-Day Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
NL-07-056, Supplement to License Renewal Application
NOC-AE-07002159, Radioactive Effluent Release Report for 2006
RA07-034, Annual Radioactive Effluent Release Report
GO2-07-078, Submittal of the 2006 Annual Environmental Operating Report
JAFP-07-0054, Annual Radioactive Effluent Release Report for the Period of January 1, 2006 Through December 31, 2006
PLA-6186, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Extended Power Uprate Application Vessels and Internals Technical Review Request for Additional Information Responses
ULNRC-05408, Update for Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
2CAN040701, Startup Test Activity Reduction (STAR) Summary Report
RA07-036, Submittal of Relief Requests Associated with the Third Inservice Inspection (ISI) Interval and the Second Containment Inservice Inspection (Cisi) Interval
U-603816, Annual Radiological Environmental Operating Report
RC-07-0074, V. C. Summer - Ninety-Day Response to GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
NRC-07-0020, Annual Radiological Effluent Release and Radiological Environmental Operating Reports
ULNRC-05403, Revision to the 2005 Annual Radioactive Effluent Release Report
HNP-07-040, Request for License Amendment to Use Other Containment Sump Water Level Instruments
L-2007-024, Application for License Amendment Request 189 (LAR 189) Regarding Incorporation of New Technical Specification 3.0.6, Administrative Controls
U-603815, Submittal of the 2006 Annual Radioactive Effluent Release Report
NOC-AE-07002161, Weld Overlay Examination Results (RR-ENG-2-43)
LIC-07-0033, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
NRC 2007-0030, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
RS-07-067, Amergen Energy Co., LLC, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
RS-07-070, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report
L-MT-07-041, Response to NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
SCH07-052, Annual Environmental Operating Report
PLA-6185, 2006 Annual Environmental Operating Report (Nonradiological.)
NOC-AE-07002160, Annual Environmental and Annual Radiological Environmental Operating Reports
HNP-07-061, G20060793 - C. S. Hinnant Ltr Shearon Harris, Unit 1, Response to Request for Comment on Proposed Directors Decision Under 10 CFR 2.206
GNRO-2007/00022, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
NL-07-0950, NRC Generic Letter 2007-01 Response
BYRON 2007-0059, Pressurizer Weld Overlay Examination Results Related to Byron Station Relief Request 13R-08
L-2007-074, 2006 Annual Environmental Operating Report
BSEP 07-0036, Transmittal of Radioactive Effluent Release Report for the Period from January Through December 2006
CPSES-200700859, Submittal of the Annual Non-Radiological Environmental Operating Report for 2006
PLA-6187, Response for Additional Information Requested in Regard to Proposed License Amendment No. 285, Constant Pressure Power Uprate Environmental
L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report
1CAN050701, Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report
L-MT-07-033, Submittal of the Core Operating Limits Report for Cycle 24
ULNRC-05400, 2006 Annual Radiological Environmental Operating Report
NLS2007036, Technical Specification Bases Changes
LR-N07-0092, Transmittal of Radioactive Effluent Release Report for 2006
NL-07-0961, Pressurizer Nozzle Full Structural Weld Overlay Evaluation
BVY 07-017, Relief Request No. ISI-PT-01, Alternate Pressure Testing for Buried Piping Components, Fourth Inservice Inspection Interval
NRC-07-0021, Annual Non-Radiological Environmental Operating Report for 2006
W3F1-2007-0019, Annual Radioactive Effluent Release Report for 2006
CNRO-2007-00021, Request for Alternative W3-R&R-006 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
CNRO-2007-00020, Request for Alternative W3-ISI-003, Proposed Alternative to Extend the Second 10 - Year Inservice Inspection Interval for Reactor Vessel Internal Weld Examinations
LR-N07-0089, Units 1 and 2 - 2006 Annual Radiological Environmental Operating Report
DCL-07-048, 2006 Annual Radiological Environmental Operating Report
W3F1-2007-0021, Annual Radiological Environmental Operating Report, 2006
CPSES-200700871, Transmittal of Year 2006 Radioactive Effluent Release Report
HNP-07-044, Annual Environmental (Non-Radiological) Operating Report for 2006
DCL-07-047, Annual Radioactive Effluent Release Report
RBG-46688, Radiological Environmental Operating Report for 2006
DCL-07-049, Annual Nonradiological Environmental Operating Report
HNP-07-051, Submittal of Information in Support of NFPA 805 Pilot Observation Reviews
L-2007-071, Reply to Request for Additional Information Re Steam Generator Tube Integrity Amendment Request
NRC-07-0014, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator - Probabilistic Risk Assessment Questions
NRC 2007-0026, Generic Letter 2003-01, Control Room Habitability Regulatory Commitment Change
L-2007-004, Proposed License Amendments, Removal of Technical Specification Reporting Requirements for License Condition Violations
JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses
NL-07-041, License Renewal Application Environmental Report References
NL-07-0067, License Amendment Request to Technical Specification 3.9.3, Containment Penetrations, Personnel Air Locks Doors Open During Fuel Movement
BYRON 2007-0052, Annual Radioactive Effluent Release Report
NRC-07-0019, 2006 Annual Reports for Fermi 2
GNRO-2007/00024, Annual Radiological Environmental Operating Report (AREOR)
GNRO-2007/00023, Annual Radioactive Effluent Release Report (ARERR)
L-HU-07-010, Transmittal of Monticello and Prairie Island, Units 1 and 2, Guarantee of Payment of Deferred Premiums
LIC-07-0025, Revised Fort Calhoun Station, Unit 1, 2007 Biennial Decommissioning Funding Status Report
LIC-07-0034, Annual Report for 2006 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46
L-MT-07-031, Annual Radiological Environmental Operating Report
ENOC-07-00013, Amendment No. 12 to Indemnity Agreement No. B-40
LR-N07-0061, Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
LR-N07-0058, Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
LR-N07-0084, Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration
RNP-RA/07-0028, Annual Radioactive Effluent Release Report Supplement - ODCM (Rev. 28)
PLA-6174, Constant Pressure Power Uprate - PLA-6174
RNP-RA/07-0025, Annual Radioactive Effluent Release Report
W3F1-2006-0066, Clarification to Request for Additional Information Regarding RF13 Steam Generator Tube Inspections
HNP-07-045, Annual Radiological Environmental Operating Report for 2006
NOC-AE-07002144, CFR50.59 Summary Report
LR-N07-0070, Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate
LIC-07-0032, Transmittal of Omaha Public Power District (OPPD) 2006 Annual Financial Report
BSEP 07-0032, NRC Correspondence Distribution List Update
NOC-AE-07002143, 1RE13 Inservice Inspection Summary Report for Steam Generator Tubing
PLA-6188, Property Insurance Program PLA-6188
RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
PLA-6154, Response to SAMA Request for Additional Information
DCL-07-045, Generic Letter 2003-01, Control Room Habitability, Commitment Change
NLS2007019, CFR 50.55a Request Number R1-29, Revision 0
NL-07-047, Withdrawal of License Amendment Request (LAR) for Indian Point Unit 2 to Add Spent Fuel Cask Loading Requirements to the Technical Specifications
RS-07-053, Request for Acceptance for Continuous Extended Power Uprate Operation
RS-07-048, Additional Information Supporting Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit
RS-07-068, Updated Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors from November 4, 2005 Through November 3, 2006
CPSES-200700517, Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change
RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
LR-N07-0028, Core Operating Limits Report - Cycle 19
NL-07-0153, Third Interval Inservice Testing (IST) Program Update
SBK-L-07064, Notification of RCS Leakage Monitoring Change
NL-07-0803, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)
HNP-07-046, Annual Radioactive Effluent Release Report for 2006
RNP-RA/07-0037, Transmittal of Core Operating Limits Report
JAFP-07-0050, Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program
PLA-6180, Response to March 9, 2007 NPDES Violation
CPSES-200700719, Nuclear Liability Insurance
BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)
BYRON 2007-0050, Cycle 14 Core Operating Limits Report
L-HU-07-012, Revision to Correspondence Service Lists for Nuclear Management Company, LLC
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
CNRO-2007-00019, Notification of Deviation from BWRVIP Guidelines
GNRO-2007/00021, Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 2007
JAFP-07-0019, License Renewal Application, Amendment 9
NRC 2007-0027, On-Site Property Insurance
NRC 2007-0018, Cycle 31 (U1C31) Core Operating Limits Report
NOC-AE-07002141, Resolution of Issues Regarding Proposed Amendment to Technical Specification 3/4.8.2 to Modify Requirements Related to Batteries and DC Systems
HCH-2007-030, Annual Environmental Operating Report
NL-07-0802, Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests
NL-07-0837, Pressurizer Nozzle Full Structural Weld Overlay Evaluation
W3F1-2007-0011, Response to Request for Additional Information on NRC Bulletin 2004-01 Regarding Alloy 600 Pressurizer Penetration Inspections
RS-07-055, Inservice Inspection Relief Request I3R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration
GO2-07-057, Decommissioning Fund Status Report
NL-07-0817, Unit 2, Cycle 19 Core Operating Limits Reports
NL-07-0653, Plants, Southern Nuclear Operating Company Reorganization Response to Request for Additional Information
CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses
NL-07-0744, Cycle 13 Core Operating Limits Report, Rev. 0
LR-N07-0069, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate
PLA-6159, Proposed Relief Request No. 3RR-14 to Third 10-Year In-Service Inspection Program
NG-07-0301, Decommissioning Funding Status Report
CPSES-200700691, Core Operating Limits Report, Cycle 13
ULNRC-05385, Response Regarding 10 CFR 50.55a Request for Relief from ASME Section XI Repair and Replacement Requirements: Proposed Alternatives for Application of Structural Weld Overlays to Pressurizer Nozzle Welds
NRC 2007-0020, 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval
L-2007-045, In-Service Inspection Plans, Use of Structural Weld Overlays as an Alternative Repair Technique Third Ten-Year Interval Unit 2 Relief Request 10
DCL-07-038, ASME Section XI Inservice Inspection Program Relief Request REP-1 U2
ULNRC-05381, Nuclear Decommissioning Funding Status 10 CFR 50.75(f)(1)
LR-N07-0067, Units 2 & 3 - Decommissioning Funding Status Report
NRC-07-0016, Decommissioning Funding Status Report for Fermi 2
RA07-012, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report
GNRO-2007/00019, Technical Specification Bases Update to the NRC for Period Dated March 30, 2007
GNRO-2007/00018, Supplement to Amendment Request, Changes to the Local Power Range Monitor (LPRM) Calibration Frequency
CNRO-2007-00018, Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc. for Year Ending December 31, 2006 - 10 CFR 50.75(f)(1)
NOC-AE-07002135, Commitment Change for Submittal of TSTF-448
RS-07-050, Additional Information Supporting Risk-Informed Inservice Inspection Relief Request
LR-N07-0071, Generation - Unit 2, Withdrawal of Inservice Inspection Program Relief Requests S2-I2-RR-B01 and S2-I2-RR-C01
PLA-6171, Decommissioning Report of Financial Assurance
LR-N07-0056, Response to Request for Additional Information Re Request for License Amendment - Extended Power Uprate
DCL-07-034, Commitment Change Summary Report
RBG-46669, License Amendment Request, Application for Technical Specification (TS) Change Regarding Ventilation Filter Testing Program (Vftp), TS 5.5.7, Control Room Fresh Air System (Crfas) Heater Wattage
BVY 07-021, Report of Bulk Chlorine Rail Shipments - 2006
LR-N07-0064, One Time License Change Request, Steam Generator Alternate Repair Criteria (17 Inch Inspection Distance.)
GO2-07-053, Response to Request for Additional Information Regarding License Amendment Request to Technical Specifications Associated with AC and DC Electrical Power
NOC-AE-07002132, 2007 Decommissioning Funding Status Report Effective December 31, 2006
SBK-L-07042, License Amendment Request 07-01 Setpoint Change for Reactor Trip System Interlock P-9
L-07-038, Decommissioning Report for Year Ending December 31, 2006
L-07-037, Decommissioning Report for the Year Ending December 31, 2006
RC-07-0043, V.C. Summer Report of Status of Decommissioning Funding (RR-1950)
L-HU-07-011, Plants, Decommissioning Funding Status Reports
L-07-056, Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update
NOC-AE-07002127, Request for License Amendment Related to Application of the Alternate Source Term
NRC 2007-0015, Nuclear Management Company, LLC Plan to Address the Safety Culture Issues at Point Beach, Units 1 and 2
PLA-6172, Proposed License Amendment for Constant Pressure Power Uprate - Supplement PLA-6172
PLA-6099, Notification of Changes to Snubber Inspection and Testing Requirements for Third 10-Year Interval In-Service Inspection Program Plan
NG-07-0270, Withdrawal of Relief Request to Allow Use of the Provisions of IWA-4132 for the Remainder of the Third 10-Year Inservice Inspection Interval and the Fourth Ten-Year Inservice Inspection Interval
L-07-042, Supplemental Information, Steam Generator Tube Rupture Analysis Update
L-2007-044, In-Service Inspection Plans Examination of Select Class 1 Piping and Valves Third Ten-Year Interval Unit 1 Relief Request 29
L-2007-040, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report
NL-07-038, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
NG-07-0257, Response to Request for Additional Information Regarding Proposed Technical Specification Changes
ULNRC-05374, Special Report 07-001 Re Historical Inoperability of Seismic Instrument SGAR0008
NOC-AE-07002136, Withdrawal of Proposed Change to Technical Specification 3.8.3.1, Onsite Power Distribution - Operating
NOC-AE-07002111, Withdrawal of Proposed Change to Technical Specification 3.7.4, Essential Cooling Water System.
NLS2007023, Fifth Biennial Report on Financial Assurance for Decommissioning Planning
DCL-07-032, Response to NRC Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Requests NDE-SLH U2 and NDE-LSL U2
CPSES-200700573, Request to Withdraw Relief Request A-7
RNP-RA/07-0032, Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria
BVY 07-018, License Renewal Application, Amendment 26
CNRO-2007-00014, Request for Alternative ANO1-R&R-010 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
L-07-043, Cycle 18-2 and Unit 2, Cycle 13-1 Core Operating Limits Mid-Cycle Revision Updates
LR-N07-0030, License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System
NG-07-0255, Withdrawal of Relief Request to Use the Provisions of Appendix Viii, Article VIII-4000, in the Evaluation of Changes in Maximum Cable Length for In-Service Inspection Examination Equipment
HNP-07-042, Revision of the Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan
CPSES-200700571, Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186)
NRC 2007-0024, License Amendment Request 248, Technical Specification 5.5.8 Steam Generator Program Supplemental Response to Request for Additional Information
NL-07-0680, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors
NL-07-0679, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors
PLA-6169, Submittal of Proposed License Amendments Re Arts/Mellla Implementation - Supplement
CNRO-2007-00012, Request for Alternative ANO2-R&R-005, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
SBK-L-07047, Decommissioning Funding Status Report
PLA-6168, Submittal of Proposed License Amendments Re Arts/Mellla Implementation - Supplement
PLA-6163, Proposed License Amendment Re Constant Pressure Power Uprate - Supplement
NRC-07-0012, Proposed License Amendment to Revise the Minimum Emergency Diesel Generator Voltage in Technical Specification 3.8.1 Surveillance Requirements
CNRO-2007-00013, Withdrawal of Request to Use ASME Code Case N-752, Risk-Informed Safety Classification and Treatment for Repair/ Replacement Activities in Class 2 and 3 Moderate Energy Systems
RS-07-041, Supplement to Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
NL-07-0678, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors
NL-07-026, Proposed Change to Fire Protection License Conditions
RNP-RA/07-0023, Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria
JAFP-07-0036, Review of Draft Safety Evaluation Related to Pending Arts/Meod Technical Specification Amendment
LR-N07-0023, Response to RAIs on LCR S06-07 Refueling Operations - Decay Time
LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate
NL-07-037, Supplement to License Amendment Request Regarding Miscellaneous Editorial Changes
LR-N07-0057, Supplemental Information on LCR S07-01 One Time License Change Request Steam Generator Alternate Repair Criteria (17 Inch Inspection Distance)
2CAN030701, Arkansas One, Unit 2, License Amendment Request, Proposed Technical Change Regarding Containment Spray Nozzle Test Requirements
DCL-06-013, Response to NRC Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Request NDE-SBR
BVY 07-015, Technical Specifications Proposed Change No. 272 - Transmittal of Final Retyped Technical Specifications Pages
L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006
NL-07-0428, Cycle 21 and Unit 2 Cycle 18, Core Operating Limits Reports, Revision 2
BVY 07-009, License Renewal Application, Amendment 24
L-HU-07-009, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time
NL-07-0626, Additional Information Regarding the Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays - Revision 2.0
ULNRC-05378, CFR 50.46 Annual Report, ECCS Evaluation Model Revisions
CNRO-2007-00009, Arkansas One, Unit 1 - Request for Alternative ANO1-ISI-008, Request to Extend the Current ASME Inservice Inspection Interval in Accordance with NRC Information Notice 98-44
CNRO-2007-00011, Request for Alternative W3-ISI-002, Request to Extend the Current ASME Inservice Inspection Interval in Accordance with NRC Information Notice 98-44
CNRO-2007-00010, Request for Alternative ANO1-R&R-010 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
HNP-07-004, Supplemental Information Regarding GL-96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions.
L-PI-07-024, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds - Supplemental Response, Revision 1
HNP-07-033, Response to the Request for Additional Information Regarding the License Amendment Request to Revise Values Associated with the Steam Generator Water Level Trip Setpoints
NOC-AE-07002126, Response to Request for Information on Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
PLA-6148, Proposed License Amendment Number 262, for Unit 2 Operating License No. NPF-22, Electrical Power Systems Technical Specification 3.8.1
LR-N07-0041, Specific Activity Analysis - 2007 Annual Report
ULNRC-05366, Correction for Previously Submitted Letters with Improper Unsworn Declarations for Satisfying Oath or Affirmation Requirements (Based on Regulatory Issue Summary 2001-18)
RS-07-039, Request for Safety Evaluation Revision Regarding Backup Stability Protection Methodology
NRC 2007-0013, License Amendment Request 248, Technical Specification 5.5.8, Steam Generator Program Response to Request for Additional Information
L-PI-07-021, Withdrawal of License Amendment Request to Reduce Monthly Test Load for Emergency Diesel Generators D5 and D6
RS-07-038, Additional Information Supporting Application for Steam Generator Tube Integrity Technical Specification Improvement
GNRO-2007/00016, License Amendment Request, Condensate Storage Tank Level-Low Setpoint Change
GNRO-2007/00017, Technical Requirements Manual Update to NRC for Period Dated March 1, 2007
SVP-07-013, Core Operating Limits Reports Cycle 19 (Revision 2)
L-2007-026, Annual Report of Reactor Coolant Specific Activity Limits for 2006
GNRO-2007/00011, License Amendment Request, Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices
CPSES-200700451, Annual Operating Report for 2006
GO2-07-038, Information Regarding Future Plans for MSIV Testing
GO2-07-036, Response to Request for Additional Information Regarding License Amendment Request to Technical Specifications Associated with AC and DC Electrical Power
PLA-6155, Proposed License Amendment Nos. 285 and 253, Constant Pressure Power Uprate Supplement
NOC-AE-07002104, Response to NRC Request for Additional Information on Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
L-PI-07-013, License Amendment Request (LAR) to Revise Technical Specification (TS) 5.2.2 and TS 5.3 Qualification Requirements for Shift Technical Advisors
RS-07-031, Response to Request for Additional Information Regarding Site-specific Decommissioning Cost Estimates
RNP-RA/07-0016, Response to NRC Request for Additional Information Regarding Proposed Technical Specifications Change to Section 3.5.2
LR-N07-0036, LCR S06-03 Supplement Request for Change to Technical Specifications Accident Monitoring Instrumentation and Source Check Definition
CNRO-2007-00006, General Electric Licensing Topical Report, NEDE-33284P, Revision 0, Marathon-5S Control Rod Assembly, September 2006
NRC-2007-0011, Refueling 28 Steam Generator Examination Report
LR-N07-0029, Supplement to License Amendment Request for Extended Power Uprate
RS-07-033, Introduction of Lead Use Channels
CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating
NRC 2007-0010, Post-Accident Monitoring Instrumentation Report Inoperability of One Channel of Containment Wide Range Pressure Transmitter
HNP-07-013, Annual Report in Accordance with Technical Specification 6.9.1.2 for 2006
NL-07-0379, CFR 50.46 ECCS Evaluation Model Significant Change Report
SBK-L-07034, 2006 Annual Report of Primary Coolant Specific Activity
SBK-L-07033, 2006 Annual Report of Removable Contamination from Sealed Source or Fission Detector
NL-07-0258, Technical Specifications Revision to Allow File Movement with Refueling Interlocs Inoperable
LR-N07-0026, Supplemental to License Amendment Request for Extended Power Uprate
BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5
ET 07-0013, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation System Controls
ET 07-0007, 90 Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
3F0507-02, Transmittal of the 2006 Radiological Environmental Operating Report
3F0407-06, 2006 Technical Specifications Bases Control Program
ET 07-0005, Results of the Fourteenth Steam Generator Tube Inservice Inspection
ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement
RS-07-034, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0507-03, Relief Request 07-003-RR, Revision 0
3F0407-13, Response to Request for Additional Information License Amendment Request 292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B.
3F0407-15, Resubmittal of Relief Requests 07-001-RR, Revision 0, and 07-002-RR, Revision 0
3F0307-10, Relief Requests 07-001-RR, Revision 0, and 07-002-RR, Revision 0
3F0407-10, License Amendment Request 296, Revision 0, Measurement Uncertainty Recapture Uprate
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
3F0307-11, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction
ET 07-0020, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
BW070040, Response to Request for Additional Information Regarding Spring 2006 Steam Generator Inspection
ET 07-0016, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
ET 07-0014, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
BW070038, Submittal of 2006 Annual Radiological Environmental Operating Report
0CAN050701, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
L-PI-07-028, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement
ET 07-0011, Response to NRC Requests for Additional Information Related to License Renewal Application
BVY 07-028, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
DCL-07-053, 90-day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
TSTF-07-18, TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011)
3F0507-06, Ninety-Day Response to GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
RS-07-059, Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2
2CAN040703, License Amendment Request to Allow the Use of Optimized ZIRLO Fuel Rod Cladding
SBK-L-07087, Revised No Significant Hazards Consideration Determination for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes
RS-07-075, Withdrawal of Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program
TSTF-07-12, Submittal of TSTF-425, Revision 1, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5
TSTF-07-17, TSTF-487, Revision 1, Relocate DNB Parameters to the Colr
RS-07-052, Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors
05000321/LER-2007-001, Unit 1, Re High Pressure Coolant Injection Inoperable Due to Component Failures
05000529/LER-2007-002, Regarding Condition Prohibited by Technical Specification - CEA Insertion Limit Exceeded
05000354/LER-2007-001, Re Low Reactor Water Level Scram
05000298/LER-2007-001, Regarding High Pressure Coolant Injection Inverter Circuit Failure Results in Loss of Safety Function
3F0407-13, Response to Request for Additional Information License Amendment Request 292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B
05000395/LER-2007-001, Regarding Manual Reactor Shutdown Due to Steam Leak at Feedwater Booster Pump Recirculation Header
05000266/LER-2007-001, Re CREFS Inoperability, Both Control Room Charcoal Filter Fans Inoperable
05000285/LER-2007-001, Re. Inoperability of a Post Accident Main Steam Line Radiation Monitor Due to Procedural Error
HNP-07-032, Response to Request for Additional Information 2.3.3.31-1 and 2.3.3.31-2 for License Renewal
05000247/LER-2007-003, Re. Plant in a Condition Prohibited by Technical Specifications Due to Operation with Control Room Ventilation System High Flow
DCL-07-037, Supplement to Request for Extension of Completion Date for Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents
05000369/LER-2007-001, Re Completion Time of Technical Specification 3.8.4 Condition a Was Exceeded on May 12, 2005
BVY 07-007, Submittal of Report Pursuant to 10 CFR 50.54(bb), Titled, Vermont Yankee Nuclear Power Station - Program for Maintenance of Irradiated Fuel
05000328/LER-2007-001, Plan Re Reactor Trip Following Closure of Main Feedwater Valve Due to Control Air Line Failure
05000368/LER-2007-001, Re Completion of a Plant Shutdown Required by Technical Specifications Because a Control Element Assembly Dropped Into the Core as a Result of a Failed Upper Gripper Coil
05000237/LER-2007-001, Regarding Unit 2s Standby Liquid Control System Tank Inoperable Due to a Small Linear Crack
05000305/LER-2007-001, Regarding Reactor Trip During Turbine Trip Mechanism Testing
05000366/LER-2007-001, Regarding Main Steam Isolation Valves Fail Local Leak Rate Testing Due to Out of Specification Internal Tolerances
05000263/LER-2007-001, Regarding Reactor Scram Due to Turbine Control Valve Housing Support Failure
CPSES-200700515, Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
05000302/LER-2007-001, Re Design Oversight Results in 10 CFR 50, Appendix R, Cable Separation Criteria Not Being Met
05000255/LER-2007-002, Re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw
05000296/LER-2007-001, Regarding Reactor Scram Due to Low Reactor Water Level Caused by Loss of Feedwater
05000251/LER-2006-002, Re Intermediate Range High Flux Trip Setpoint Exceeded Technical Specifications Allowable Value
BW070019, Pressure and Temperature Limits Reports (Ptlrs), Revision 4
W3F1-2007-0014, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Refueling Outage 14
05000336/LER-2006-008, Regarding Scaffold Impairment of Turbine Driven Auxiliary Feedwater Pump Room HELB Blowout Panel
05000247/LER-2007-002, Regarding Technical Specification Prohibited Condition Due to Exceeding Containment Air Temperature Limit Allowed Outage Time as a Result of Changes in Instrument Uncertainty
05000305/LER-2006-012, Regarding Reactor Trip from Loss of Instrument Bus
05000324/LER-2006-003, Re Automatic Reactor Scram Due to Trip from Neutron Monitoring System
05000425/LER-2007-001, Regarding RWST Sludge Mixing Valves Was Determined to Be in a Condition Which Was Prohibited by TS
05000336/LER-2006-006-01, Regarding Scaffolding Built for Work on Main Steam Isolation Valve (2-MS-64A) Prevented the Valve from Closing
CPSES-200700422, Response to Request for Additional Information Related to Txu Powers Request for Review of Previously Submitted Topical Reports
05000296/LER-2004-003, Regarding Main Steam Relief Valve Inoperability LCO Exceeded During Operating Cycles 10 and 11 Due to Setpoint Drift
05000255/LER-2007-001, Failure to Perform Offsite Power Source Check
05000413/LER-2006-003, Re Technical Specification Violations Associated with Hydrogen Ignition System
05000498/LER-2006-006, Re Inoperable Auxiliary Feedwater Flow Instrumentation
05000529/LER-2006-006, Regarding Technical Specification 3.7.7 Violation - Inoperable Essential Cooling Water Heat Exchanger
05000305/LER-2007-002, Regarding Issues with Amag/Westinghouse Calculations for Full Power Result in Reduced Power Operation
05000440/LER-2006-006, Re Primary Containment Airlock Door Inoperability Results in Operation Prohibited by Technical Specifications
CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program
05000323/LER-2006-004, Regarding Automatic Reactor Trip Due to Circulating Water Pump Surge Capacitor Failure
RBG-46493, Supplement to License Amendment Request (LAR) 2006-03, Leakage Rate Testing of Containment Purge Valves
05000354/LER-2006-005, Drywell Hoist Breaker Not Open Prior to Operational Condition 2 Entry
05000260/LER-2005-008, Re Main Steam Relief Valve Inoperabilty LCO Exceeded During Operating Cycles 11, 12, and 13 as a Result of Lift Setpoint Drift
05000317/LER-2006-005, Re Startup Rate Trip Bypass Enabling Function Below Setpoint
05000338/LER-2007-001, Re Reactor Trip Due to Steam Generator Low Level Coincident with a Steam Flow Feed Flow Mismatch
05000317/LER-2007-001, Regarding Reactor Coolant System Pressure Boundary Leakage in Pump Cover Heat Exchanger
05000289/LER-2006-003, Re Automatic Reactor Trip Due to a Design Application Deficiency within the Reactor Coolant Pump Power Monitors Initiated by an Off-Site Grid Disturbance
05000247/LER-2007-001, For Indian Point, Unit 2, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Residual Heat Removal Pump Due to an Electrical Supply Breaker Failure
05000260/LER-2007-001, Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test
RS-07-006, Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program
NUREG-1427, Note to File: Docketing of Web References for NUREG-1427, Supplement 26 Regarding Monticello Nuclear Generating Plant
GNRO-2007/00031, To Amendment Request, Changes to the Local Power Range Monitor (LPRM) Calibration Frequency