DCL-16-077, Pacific Gas and Electric Companys Notification of Full Compliance with Commission Order Modifying Licenses with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) for Diablo Canyon Power Plant Un
CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001
Information Notice 1985-55, Revised Emergency Exercise Frequency Rule
L-PI-15-041, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
L-2014-303, Response to Request for Additional Information Re License Amendment Request No. 216 - Transition to 10CFR50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
NRC 2013-0038, Submittal of 2012 Annual Monitoring Report
L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 15, Accident Analysis
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 15, Accident Analyses
L-06-068, Annual Environmental Operating Report, Non-Radiological
L-03-066, Annual Environmental Report, Non-Radiological
IA-99-314, Provides List of Questions & Comments Re Gnm & Assoc That Came During Review of Proposed Cost of OWFN Marble Insp & Rept
JAFP-96-0336, Forwards Attachment Ii,Rev 1 to JPN-96-003, Instrumentation & Miscellaneous Sys Se. Changes Made by Rev,Submitted
B10942, Forwards Response to Request for Addl Info,Question E291.19, Consisting of Documented Telcons Re Environ Rept - OL Stage
JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl
0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs
05000305/LER-1985-019, :on 851107,at 100% Power,Test of Undervoltage Trip Attachment Conducted for Each Reactor Trip Breaker to Verify Existence of 20 Oz of Force Margin,Per IE Bulletin 85-002.Two Breakers Failed
05000352/LER-1984-002-02, :on 841031,during Fuel Loading W/Reactor at 0% Power & Control Rods Fully Inserted,Full Scram Occurred W/Audible Alarm Indicating Upscale Trip of IRM Channel B. Caused by Personnel Error.Technician Counseled
05000333/LER-1983-003-03, /03L-0:on 830111,while Conducting Surveillance Testing on Core Sparger to Reactor Vessel D/P Switches 14DPIS-43A & B,Instrument Setpoints Found to Be Less Conservative than Required.Caused by Instrument Drift
05000440/LER-1994-020-01, :on 940831,diesel Generator Was Inoperable. Caused by Personnel Error.Disciplinary Action Was Taken Against Control Room Unit Supervisors
BECO-93-137, Forwards Third Rept on Status of Efforts to Establish Replacement Facility for Wellesley Reception Ctr
AECM-81-312, Forwards Proposed FSAR Changes & Additions,Response to Auxiliary Sys Branch Question 10.29 & Discussion of Perched Aquifer Recharging.Proposed FSAR Changes Will Be Incorporated in Next Available Amend
TXX-3502, Forwards Tables 1 & 2 Re Functional Capability of Class 2 & 3 Austenitic Stainless Steel Pipe Bends & Elbows
GO2-89-158, Forwards Addl Info Re Underground Fire Main Analysis.Based on Results of Analyses,No Thrust Block Necessary for 12-inch Fire Main FP-43-1.ASME Rept, Flexibility Analysis of Buried Pipe, Encl
SCH10-105, New Jersey Pollutant Discharge Elimination System Discharge Monitoring Report for August 2010
NLS2003068, 2 to EPIP 5.7.17, Dose Assessment, and Revision 17 to EPIP 5.7.20, Protective Action Recommendations
B18824, Revised Emergency Plan Procedures, Attachments 1 - 6
NRC 2005-0004, Response to Request for Additional Information Regarding the Point Beach Nuclear Plant License Renewal Application and Request for Withholding of Proprietary Information from Public Disclosure
05000272/LER-1989-027, :on 890619,reactor Trip on Steam Generator 13 lo-lo Level Occurred Due to Closing of Valve 13MS167.Caused by Inadequate Design of Continuity Check Circuitry for MS167 Valves.Design Change Implemented