RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report
AEP-NRC-2015-01, Steam Generator Tube Inspection Report
W3F1-2014-0033, Core Operating Limits Report Cycle 20 Revision 0, Waterford Steam Electric Station, Unit 3
DCL-16-004, Diablo Canyon, Units 1 and 2 - Revisions to Emergency Plan (Enclosures 4, 5, 6, 7, 8, 9 & 10)
LR-N08-0032, Request for Exemption from 10 CFR 50.82(a)(8)(i) and (Ii), NRC Regulations to Permit the Immediate Withdrawal of Certain Funds from Nuclear Decommissioning Trust Funds
RS-05-062, Additional Information Supporting the Request for License Amendment Related to 21-Month Fuel Cycle
0CAN078904, Forwards Response to Violations Noted in Insp Repts 50-313/89-20 & 50-368/89-20.Response Withheld (Ref 10CFR2.790)
B16757, Provides 12 Month Special Rept Per TS 4.4.5.5.b & 6.9.2 Re Steam Generator Tube ISI Rept
JPN-97-019, Provides Summary of Detailed Evaluation of Postulated Scenarios Described in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions & CA for JAFNPP IAW Ref Commitment
ST-HL-AE-1882, Forwards Draft Rev 2 to Tech Specs Identified for Further Comment or Resolution During NRC 870107 Site Visit. Justifications Also Encl
AECM-88-0064, Application for Amend to License NPF-29,revising Tech Specs Re Mode Changes,Inconsistent Application of Exceptions & Unnecessary Shutdowns When Surveillance Intervals Inadvertently Exceeded,Per Generic Ltr 87-09.Fee Paid
ST-HL-AE-2608, Responds to Violations Noted in Insp Rept 50-498/88-09. Corrective Actions:Evaluation of Maint Work Request Generation & Approval Process Performed,Cases Where Testing Frequency Changed Verified & 1TSP03-CV-0001 Generated
3F1192-07, Requests NRC Approval of Temporary non-code Repair to Moderate Energy Portions of Nuclear closed-cycle Cooling Sys.Util Separately Filed Response to GL 90-05 Which Addresses Handling of Repairs.Response Awaited
RBG-20-430, Forwards Revs to Fsar.Revs Reflect Change in Calculations for UHS Max Temp Due to Revs in Plant Equipment Operation
3F0496-04, Submits Notifications to NRC Prior to Plant Ascension Into Mode 4 Re Number of Tubes Plugged & sleeved,crack-like Indications in First Span & Assessment of Growth for First Span Iga Indications
VPN-037-98, Submits Response to NRC Request for Addl Info Re Transportation of Trojan Reactor Vessel Package for Disposal.Update to Rv Package SAR Provided as Encl 2
3F1183-08, Forwards Revised Pages 12,28 & 42 to Detailed Control Room Design Review Program Plan,Per 831031 Submittal Re NUREG-0737,Item I.D.1, Control Room Design Reviews
LIC-95-0018, Forwards OPPD Annual Accounting for Period of Jan-Dec 1994, as Required by FCS Decommissioning Funding Plan Trust Agreement
ST-HL-AE-1223, Forwards Complete Attachment 2 of Util Responding to Environ & Hydrologic Engineering Branch Request for Addl Info
SNRC-1055, Forwards Monthly Status List of Active safety-related Equipment at Qualification Level,Per SER Issue 8, Dynamic Qualification
05000338/LER-1980-025-03, /03L-0:on 800215,channel III Steamline Pressure Protection Bistable for P2 Greater than P1 Safety Injection Initiation Tripped at Unacceptable Setpoint.Caused by Setpoint Drift in Signal Comparator Card Circuitry
BYRON 2018-0027, Steam Generator Tube Inspection Report for Refueling Outage 20
05000249/LER-1988-005-03, :on 880326,HPCI Sys Made Inoperable to Facilitate Preplanned Preventive Maint Testing.Caused by Mgt Decision to Perform Preventive Maint Testing of HPCI Turbine Overspeed Trip Sys.Hpci Tripped on 5,015 Rpm
L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
BYRON 2015-0013, Steam Generator Tube Inspection Report for Refueling Outage 18
L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
L-13-058, Steam Generator Inspection Report - Technical Specification 5.6.6.2.1
NLS2017032, 10 CFR 50.55a Request Number RI-21, Revision 1
BW070005, Twelfth Refueling Outage Steam Generator Inservice Inspection Summary Report
NL-04-1302, Inservice Inspection Summary Report
ULNRC-04826, Union Electric Annual Financial Report
NRC-94-4249, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs 940407,15,29,0505,11,16,23 & 0608. Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
W3P87-2060, Forwards Changes to QA Program (FSAR Section 17.2) Re Significant Transition at Facility from Const to Operations Phase Which Included Major Reorganization of Nuclear Operations Dept.Fee Paid