DCL-16-004, Diablo Canyon, Units 1 and 2 - Revisions to Emergency Plan (Enclosures 4, 5, 6, 7, 8, 9 & 10)
ULNRC-06349, Callaway, Unit 1 - Enclosure 3 to ULNRC-06349 - Document A22-1690-001, Rev. 0, Decommissioning Cost Analysis for the Callaway Energy Center, Appendix C, Page 4 of 10 - Appendix E, Page 7 of 10
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
ST-HL-AE-1426, Forwards Response to Draft SER & FSAR Items Re NSSS Scope of Equipment qualification.Marked-up Encl FSAR Pages Will Be Incorporated in Future Amend to FSAR
05000321/LER-1987-009, :on 870427,primary Containment Penetrations Found Leaking in Excess of Leakage Requirements.Caused by Normal Use & Wear.Valves Either Cycled,Repaired,Rebuilt, Replaced or Plugged Until Replacement
NSD-NRC-97-4947, Submits Refs & Changes for SSAR Chapter 7.Encl 1 Will Be Included in SSAR Rev 11.NRC Requested to Review Encl 2 & Provide Westinghouse W/Nrc Status for Item,Including 1052 & 1053 for Interlocks
05000267/LER-1985-009, :on 850603,Loop 1 Automatic Shutdown Initiated by Plant Protective Sys.Caused by Short of Intermodular Connections Between Two Loop Trouble Logic Modules. Connections Repaired
NRC-90-0159, Comments on Draft Generic Ltr 88-20,Suppl 4, Individual Plant Exam of External Events (IPEEE) for Severe Accident Vulnerabilities, & NUREG-1407.Util Shares Concern That IPEEE Will Place Enormous Burden on Technical Resources
05000333/LER-1979-006-03, /03X-1:on 790124,during Normal Operations,Ground Fault on 125 Station Battery a Noted.Caused by Bellows Failure on Pressure Switch Circuit safety-relief Valve 02-RV-71J.Ground Cleared.Valve Restored to Operation
05000251/LER-1989-006-01, :on 890713,intake Cooling Water Flow to Component Cooling Water HXs Degraded Below Design Basis Flow Rate for 15 Minutes.Caused by Failure of Header Isolation Valve 4-50-308.Valve Replaced & Pin Removed
L-83-523, Forwards Revised Tech Spec Page Re RHR Pump Operability Per 831013 Telcon Request for Addl Info Concerning Proposed License Amend
L-86-354, Forwards Response to 860807 Request for Addl Info Re 860715 Application to Amend License NPF-16,revising pressure-temp Limits for RCS
W3F1-2016-0064, Mitigating Strategies Assessment (MSA) Report for Flooding Hazard
E900-03-016, Rev 0 to Calculation E900-03-016, Shinka Discharge & Intake Tunnels FSS Survey Design, Appendices a - C to Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Intak
RNP-RA/02-0028, Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval
NL-03-0684, ASME Section XI Requests for Relief Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head
BECO-87-158, Responds to 870714 Request for Addl Info Re Second 10-yr Interval Inservice Insp Program Plan.Ref List of Calibr Blocks,Including Identifications,Matl Specs & Sizes Encl