PLA-7384, Proposed Amendment No. 292, Temporary Change to Allow Replacement on Unit 1 480 V Ess Load Center Transformers in Unit 2 Technical Specifications 3.8.7 and 3.7.1
BSEP 13-0010, Attachment 1: Requested Drawings
L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating
BSEP 11-0028, Response to Request for Additional Information Regarding Proposed Exemption from Certain Requirements of the Fitness for Duty Rule for Managing Fatigue
NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
JAFP-09-0070, Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time
L-77-380, Response to Request for Additional Information System Disturbance
B12183, Forwards Comments on Draft Ol,Draft Suppl to NUREG-1143 & Tech Specs,Per 860530 Request.Proposed Tech Specs Reflect Existing Configuration of Plant
B11747, Forwards Review of Integrated Safety Assessment Program Topic 1.25, Degraded Grid Voltage Procedures, Resulting from Review of SEP Topics VIII-1.A & VII-3 Per 850517 Commitment
JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
05000293/LER-1992-016, :on 921213,automatic Scram Resulting from Load Rejection Occurred While at 48 Percent Reactor Power.Caused by 345 Kv Switchyard Flashovers Due to Salt Deposited During Severe Coastal Storm
05000324/LER-1994-008-02, :on 940521,dispatcher Switching Evolution Resulted in Loss of Offsite Power.Instructions for Any Planned Switching Activity at Nuclear Power Plant Will Require Dual Verification
05000370/LER-1993-008-03, :on 931227,Unit 2 Reactor Trip Occurred Due to Loss of off-site Power.Caused by Unanticipated Environ Interaction,Vendor Fabrication Deficiency,Deficient Documentation & Inadequate Surveillance Program
05000293/LER-1993-016, :on 930719,HPCI Sys Declared Inoperable.Caused by Depiction & Description of Field Common Connections on Panalarm Co Drawing.Field Common for Alarm Circuit re-established & Tested
05000293/LER-1993-014, :on 930531,automatic Scram Occurred,Resulting from Operation of Auxiliary Transformer Differential Relay During Power Ascension.Uat Phase B & C Differential Relays Left Interchanged as Investigative Aid
05000293/LER-1990-008, :on 900513,automatic Scram Resulting from Load Rejection Occurred While at Full Power,Resulting in Trip of Generator Field Breakers.Caused by Fault on Offsite 345 Kv Transmission sys.Loss-of-field Relay Replaced
LD-93-071, Forwards Suppl 1 of Sys 80+ Design Descriptions & ITAAC (Insps,Tests,Analyses & Acceptance Criteria).Changes Expected to Be Incorporated in Final Amend Targeted for Submittal on 930630
05000293/LER-2016-002, Regarding Online Maintenance Test Configuration Prohibited by Technical Specifications
L-11-331, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating
PLA-2961, Forwards Rept Summarizing 1986 Approved Safety Evaluations, Per 10CFR50.59