RS-16-176, County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ic
RS-14-006, Updated Safety Analysis Report, Revision 16, CPS Operational Requirements Manual
RS-13-009, Operational Requirements Manual (Orm) 2013
L-18-046, License Amendment Request to Extend Containment Leakage Test Frequency
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control Systems
RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report
RA18-059, Inservice Testing Program Plan, Technical Position TP-05
L-09-158, Ninety Day Post-Outage Supplemental Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
RS-19-066, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency
GNRO-2004/00002, Technical Specification Bases Update to the NRC for Period Dated January 22, 2004
L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
U-600589, Forwards Details Re Operator Actions Following Evacuation of Main Control Room & Safe Shutdown from Remote Shutdown Panel,Per Request,Including List of Assumptions & Approx Times for Specific Actions for Scenario
U-600590, Part 21 & Deficiency Rept 21-85-18 Re Anchor/Darling,Velan, Atwood-Morill & Walworth Valve Cos 410 Stainless Steel Valve Stem Corrosion Failures.Valves Tested for Stem Hardness & Cracks & Hard Stems Replaced
U-603072, Forwards Response to RAI Re ASME Section XI Relief Request for Testing of Selected Category a Isolation Valves During First 120-month ISI Interval for CPS
U-601167, Forwards Addl Info Relating to Questions on Pneumatic & Hydrostatic Testing of Containment Isolation Valves & Pressure Isolation Valves.Info on Stroke Times of Certain Valves to Be Evaluated by NRC Also Encl
U-600275, Forwards marked-up Proof & Review Tech Specs,Per 850904 Request,Indicating Typos & Corrections to Info Submitted in 840928 & s
U-600286, Forwards Sept 1985 Monthly Update of Seismic Qualification /Instrument Status by Sys/Equipment Number, Per Generic Open Item 5,850924 Sqrt Ltr & SER Outstanding Issue 7ii
U-601958, Forwards Revised Response to Suppl 3 of Bulletin 88-008 Re Thermal Stratification in Unisolable Piping Connected to RCS W/Respect to Action 3 of Bulletin,In Response to NRC
AECM-83-0381, Notifies of Compliance W/Operating License Condition 2.C(12)(c)(i) & (Iii).Updated Status List of Environmental Qualification Equipment Important to Safety Encl
JSP-552-93, Part 21 Defect 21-93-029:on 931007,discovered Broken Motor Shaft Pinion Key in Limitorque Actuator of motor-operated HPCS Sys Injection & Outboard Containment Isolation Valve 1E22-F004.Broken Motor Pinion Key Replaced
PY-CEI-NRR-0389, Comments on Final Draft Tech Specs Per .Changes Discussed W/Nrc Tech Spec Review Group Reviewer
PY-CEI-NRR-0261, Forwards Updated Deviation Requests to 10CFR50,App R Re Fire Protection Program.Encl Deviation Requests Replace Requests Submitted on 820616 & 830324.Response Requested by 850628
05000440/LER-1987-025, :on 870407,outboard Containment Isolation Valves for RHR Sys a Automatically Isolated.Caused by High Pressure Signals from Loose Signal Connection.Single Common Wire Properly Connected to Signal Common Bar
05000440/LER-1986-048, :on 860819 & 20,unexpected RHR Sys Isolations Occurred During Performance of Maint Retest.Caused by Inadequate Surveillance Test Instruction (Svi) & Poor Jumper Connection,Respectively.Svi Revised
05000373/LER-1985-053-01, :on 850717,RHR Shutdown Cooling High Suction Flow Switches 1E31-NO12AA/AB/BA/BB Discovered Piped in Reverse of Sys Design & Inoperable.Caused by Failure to Revise Design Drawing.Drawing & Piping Revised
05000461/LER-1990-017, :on 901206,RHR Sys Not Bypassed During Performance of HX B Room Differential Temp Channel Calibr. Caused by Procedural Errors.Individuals Counseled
05000373/LER-1983-152-03, /03L-0:on 831130,shutdown Cooling Inboard Isolation Valve IE12-F009 Exceeded Allowable Leakage Limit. Caused by Bottom Seat Ring Sealing Surface Not Adequately Flat.Ring Machined to Assure Flatness
05000440/LER-2010-001, Regarding Invalid Isolation Signal Results in Shutdown Cooling Interruption
L-91-004, Additional Information Supporting the Request for License Amendment Related to 24-Month Fuel Cycle
L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing
PY-CEI-NRR-0716, Informs That Testing & Review of Updated Inservice Testing Program for Pumps & Valves Identified Need for New Relief Requests.Listing of New & Revised Relief Requests Encl.Fee Paid