DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of Operations
E910-05-064, Experimental Corporation 2005 Radiological Environmental Monitoring Report
E910-05-011, Experimental Corporation, 2004 Radiological Environmental Monitoring Report
BVY 05-023, Licensee Post Exam Comments & NRC Resolution (Folder 1)
E910-04-016, Experimental Corporation (Snec), 2003 Radiological Environmental Monitoring Report
E901-03-018, Radiological Environmental Monitoring Report
E910-02-054, Experimental Corporation (SNEC) Application for License Termination
E910-02-046, Decommissioning Environmental Report, Revision 2
E910-02-019, Radiological Environmental Monitoring Report
JPN-90-077, Forwards Response to 900518 Request for Addl Info Re Reliability of Manual Bus Transfers Between Onsite & Offsite Power Supplies
NLS8900379, Forwards Info Re Sims for Plant,Per Project Manager Request
B13231, Rev 2 to First 10-Yr Interval Inservice Insp Plan Summary
3F0997-14, Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR
DCL-85-141, Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Table of Contents & Rev 0 to EP E-0, Reactor Trip or Safety Injection. Privacy/ Proprietary Info Identified in Encl.Related Correspondence
3F0597-31, Responds to NRC Re Violations Noted in Insp Rept 50-302/97-04.Corrective Actions:Training & Full Implementation of Revised Corrective Action Process Is Scheduled for Completion by 970601
E910-02-003, Experimental Corporation, Supplemental Response to RA3 Questions
E910-02-005, Supplemental Response to RAI 2 Questions
BVY 04-019, Revision 20, LPC1 to OP 3524, Emergency Actions to Ensure Initial Accountability and Security Response and Revision 2, LPCI1 to Operation of the Technical Support Center(Tsc).
05000456/LER-1997-009-07, :on 971028,potential Failure of W Fuel Rod Design Criteria Discovered.Caused by W Use of Inadequate Methods & Incorrect Assumptions in Fuel Rod Design Code.W Developed Plan to Resolve Fuel Rod Issue
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
05000333/LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure
05000364/LER-1991-002, :on 910409,reactor Manually Tripped Following Loss of Operating Steam Generator Feedwater Pump.Caused by Failed Eh Fluid Supply Line Coupling & Loss of Eh Fluid.Eh Tubing Repaired
05000324/LER-1990-010-02, :on 900822,reactor Protection Sys Bus a Deenergized During Cold Shutdown.Caused by Personnel Error. Operators Disciplined & Clearance Procedure Will Be Revised to Clarify Double/Independent Verification
TXX-8985, Corrects 891221 Response to Case 891206 Request for Action Scaling Calculations.Nrc Should Deny Request
PLA-3623, Submits Util Calculation FQ-C-JAN-002, Evaluation of Out of Limit RPV Cooldown/Heatup Rate Occurring on 890112
05000316/LER-1996-001, :on 960216,determined Alarm Setpoint of Radiation Monitor Set Incorrectly.Caused by Failure to Fully Integrate Regulatory Requirements of 10CFR70.24 Into Plant Design.Setpoint Adjusted
05000397/LER-1997-002, :on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr Procedures
05000335/LER-1979-019-03, /03L-0 on 790605:control Element Assembly Dropped Four Times within 2-h Period.Caused by Failure of Coil Power Programmer Timing Module.Module Replaced
BVY 04-019, 0, Lpc 1 to OP 3524, Emergency Actions to Ensure Initial Accountability and Security Response and Revision 2, LPCI 1 to Operation of the Technical Support Center(Tsc)
E910-02-003, Experimental Corporation, Supplemental Response to RA 3 Questions