RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
05000280/LER-1990-017, :on 901202,loss of 4,160-volt Transfer Bus F Occurred.Caused by Personnel Error.Appropriate Training & Procedural Enhancements Are Being Undertaken
B16136, Application for Amend to License DPR-21,changing Plant,Unit 1 Instrument Calibration,Functional,Response Time,Resistance Temperature Detector & Thermocouple Testing Requirements & Clarifies Srs,Thereby Helping to Ensure Proper Testing
B17007, Provides Emphasis for Statements & Descriptions Addressed in NNECOs LAR & Accompanying NSHC Determination That NRC SER for License Amend 102 Does Not Explicitly Address
05000219/LER-1995-009, :on 960103,two APRM Were Inoperable Due to Lack of Complete Understanding of Circuitry.Addl Training on APRM Sys Provided & Quarterly Surveillance Test & Vendors Manual Revised
05000331/LER-1983-046-03, /03L-0:on 831201,reactor Protection Sys Electric Assembly B2 Failed to Trip Output Breaker at Required Frequency.Caused by Setpoint Drift.Test Results Will Be Monitored
05000333/LER-1983-008-01, /01T-0:on 830202,error in Odyn Base Deck for Reload 4 Analysis Caused Delta Critical Power Ratios for Pressurization Transients to Be Nonconservative.Caused by Improper Data Input Due to Personnel Error
05000321/LER-1982-013-03, /03L-0:on 820213,during Startup,Average Power Range Monitor Not Adjusted within 2-h Time Limit & Corrective Action Ineffective.Caused by Spatial Redistribution of Xenon & Faulty Rod Pattern Adjustment
BECO-90-101, Application for Amend to License DPR-35,changing Tech Specs by Removing cycle-specific Parameter Limits & Relocating to Core Operating Limits Rept
05000282/LER-1990-002, :on 900117,review of Cooldown Data Showed That Cooldown Rate of Pressurizer Exceeded Tech Spec Limit.Caused by Procedure Inadequacy.Procedures Revised to Require Use of Water Space Temp to Find Cooldown Rate
05000281/LER-1995-001-02, :on 950204,pressurizer Heatup Exceeded TS Limit Due to Lack of Procedural Control.Cooldown Rate Reduced, Deviation Rept Submitted & Plant Data for Event Supplied to Westinghouse to Peform Technical Evaluation
05000281/LER-2011-002, For Surry Power Station, Unit 2, Regarding Spurious Safety Injection Results in Exceeding Pressurizer Heatup Rate
05000280/LER-2011-001, Regarding Reactor Trip on Both Units Due to Loss of Offsite Power
05000247/LER-2000-001, Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000
NL-02-001, License Amendment Request - Detection of Technical Specifications for Reactor Vessel Material Surveillance Program