W3F1-2016-0071, Responses to Request for Additional Information Set 4 Regarding the License Renewal Application
CP-201700225, Guarantees of Payment of Deferred Premiums
CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera
L-PI-16-090, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change
CP-201800087, Submittal of Guarantees of Payment of Deferred Premiums
TMI-15-065, Notice of Transfer of Transmission Assests
L-2014-071, Response to Request for Additional Information License Amendment Request No. 216 - Transition 10 CFR 50.48(c)-NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants(2001 Edition)
NLS2013104, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Cooper Nuclear Station
RS-12-075, Response to Request for Additional Information Regarding Relief Request 14R-19 and Additional Followup Question on the Flaw Evaluation
NRC 2011-0039, Redacted - Point Beach, Units 1 and 2, Submittal of 2010 Annual Monitoring Report
NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9
LR-N10-0294, Response to Request for Additional Information - License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension
LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
LR-N08-0043, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
NL-07-124, Supplement to License Renewal Application (LRA)
W3F1-2005-0063, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
L-15-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
AECM-88-0107, Forwards Computer Tape of Hourly Meteorological Data for 1987.Note Tape Formatted Similar to Tape Sent Earlier by Ltr Except That Ebcdic Format Rather than Ascii Format Used.Sample Tape Dump Printout Also Encl
ST-HL-AE-3916, Requests Exemption from Requirements of 10CFR50.62, Eliminating Requirements for Specific ATWS Mitigating Sys Actuation Circuitry.Proprietary Pages to Rev 0 to WCAP-12385 Encl.Encl Withheld
LD-93-174, Responds to Request of NRC Staff & Forwards Five Copies of Selected CESSAR-DC Parameters & Assumptions Addressed in Certified Design Matl for System 80+ Standard Plant Design
ULNRC-06011, Responses to RAI Set 3 Regarding Adoption of National Fire Protection Association Standard NFPA 805
05000260/LER-1989-019, :890623,loop II of RHR Sys Technically Inoperable When Operability Required by Tech Specs.Caused by Inadequate Tracking & Dispositioning of Test Deficiency. Signature Requirements Added to Test Packages
05000424/LER-1987-076, :on 871127,instrument Panel 1-1513-P5-HMA Inoperable for More than 7 Days.Caused by Personnel Error. Personnel Counseled on Control & Temporary Storage of Matls During in-process Work
0CAN058402, Annual Environ Radiological Monitoring Rept,1983
GO2-83-622, Forwards Info Re as-built Seismic Category I Quality Class II Hangers,Spec Requirement & Documentation Relative to hold-down Bolts for Reactor Vessel to Assist in Resolution of Issues Raised by Const Assessment Team
05000369/LER-1990-028-01, :on 901023,ice Basket U-bolts Found Damaged or Missing Due to Matl Deficiency
05000213/LER-1993-010, :on 930629,loss of Power During Surveillance Testing Occurred Due to Blown Fuse.Blown Fuse Replaced
05000206/LER-1981-029, Forwards LER 81-029/03L-0.Detailed Event Analysis Submitted
NUREG-0063, Forwards Addendum to NUREG-0063, Fes Re Operation of William B McGuire Nuclear Station,Units 1 & 2
05000219/LER-1981-001-03, /03L-0:on 810102,containment Spray Sys High Drywell Pressure Indicating Switch IP-15C Tripped Above Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset & Study Examining Causes of Repeatability Undertaken
STC-24-062, Issuance of Proposed Rule and Notice of Availability of the Draft Generic Environmental Impact Statement
GO2-99-015, Provides Addl Info to Support Staff Review of 981217 Request for Rev to TS SR 3.8.1.8,allowing for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 When Required for Equipment Testing
L-98-211, Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
CNL-17-003, Update to the TVA Response to NRC Letter Re Chilled Work Environment for Raising and Addressing Safety Concerns at the Plant
NL-04-0564, And Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors
RS-03-140, Request for Amendment to Technical Specifications Associated with Direct Current Electrical Power
BSEP 02-0067, Response to Request for Additional Information Regarding Request for License Amendments - Extended Power Uprate
STC-24-058, Issuance of Proposed Rule and Notice of Availability of the Draft Generic Environmental Impact Statement for Advanced Nuclear Reactors (NUREG 2249)
L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses
BECO-87-158, Responds to 870714 Request for Addl Info Re Second 10-yr Interval Inservice Insp Program Plan.Ref List of Calibr Blocks,Including Identifications,Matl Specs & Sizes Encl
05000213/LER-1986-041, :on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg