W3F1-2006-0012, Report of Facility Changes, Tests and Experiments and Commitment Changes
| ML061280070 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/01/2006 |
| From: | Tankersley T Entergy Nuclear South |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2006-0012 | |
| Download: ML061280070 (5) | |
Text
" ftergy Entergy Nuclear South Entergy Operations. Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6783 Fax 504-739-6693 ftanker@entergy.com Tom Tankersley Licensing Manager Waterford 3 W3Fl -2006-0012 May 1, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Report of Facility Changes, Tests and Experiments and Commitment Changes Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Enclosed is the summary report of facility changes, tests and experiments for Waterford 3, which is submitted pursuant to 10CFR50.59 (d)(2). This report covers the period from June 1, 2C004 through April 1, 2006. This submittal also includes a CD-ROM of the I OCFR50.5s Evaluation for each change and a summary report of Commitment Changes for the same time period.
If you have any questions regarding this report, please contact Michael E. Mason at (504) 739-6673.
There are no new commitments contained in this submittal.
Sincerely, TET.'MEM/cbh Attachment(s)
.rE 4-7
W3F1 -2006-0012 Page 2 cc:
(w/Attachment - CD Rom)
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. Mel B. Fields Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 W3Fl -2006-0012 Waterford 3 10 CFR 50.59 Summary Report to W3F1-2006-0012 Page 1 of 2 1 OC:FR50.59 Evaluation Number 04-C004 04-005 04-C007 04-C008 04-C009 05-001 05-C'02 05-C003 05-C104 05-C005 05-C106 Initiating Document Amendment 91 Amendment 92 Calculations EC-M88-021 and EC-E89-016 ER-W3-2001-1149-005 ER-W3-2001-1149-01 0 ER-W3-2004-1129-015 ER-W3-2001-1149-009 ER-W3-2004-01 37-000 ER-W3-2004-0276-000 ER-W3-2004-0478-000 ER-W3-2004-0602-000 Summary New TRM 3.0/4.0 Section, Remove Shutdown Requirements From TRM Move Pressurizer Heat-up and Cooldown Limits to TRM and Remove Shutdown Requirements Station Blackout Water Requirements From Extended Power Up-rate Extended Power Up-rate Impact To FSAR Chapter 5 Extended Power Up-rate Impact To FSAR Chapter 10 Extended Power Up-rate Impact To FSAR Chapter 15 Extended Power Up-rate Impact To FSAR Chapter 9 In Core Instrumentation Thimble Support Plate Modification Alternate Source Term Implementation Steam Generator Sub-compartment Platforms Addition Impact Steam Generator Feedwater Pump Trip Logic Modification Due To Extended Power Up-rate 05-C107 05-C108 05-C109 05-01 1 05-C1 2 05-01 3 05-C1 4 05-015 05-C1 6 05-017 ER-W3-2004-01 22-000 ER-W3-2005-001 9-000 ER-W3-2003-0662-000 ER-W3-2005-0083-000 ER-W3-2004-01 16-003 ER-W3-2003-0053-000 ER-W3-2002-0595-000 ER-W3-2005-01 30-000 License Amendment Request NPF 38-249 Core Operating Limits Report and Startup and Setpoint Transmittal for Cycle 14 Pressurizer Heater Sleeves And Instrument Nozzles Weld Repair Steam Generator Level Set-points Modification Due To Extended Power Up-rate 480 Volt Safety Buses Limit Change When On Startup Transformers Health Physics Calculations Implementation From Extended Power Up-rate And Alternate Source Term Core Next Generation Fuel And Lead Test Assemblies From Reload Analysis Report High Pressure Turbine Design Upgrade For Extended Power Up-rate Main Generator Output Breaker Modification From Extended Power Up-rate Temporary Alteration For Keeping Circulating Water System Operating Technical Requirements Manual and Final Safety Analysis Report change due to Extended Power Up-rate Changes To Moderator Temperature Coefficient, Linear Heat Rate, Departure From Nuclear Boiling Rate Margin, Axial Shape Index; Revised Core Operating Limit to W3F1 -2006-0012 Page 2 of 2 05-018 05-019 05-020 05-021 05-022 05-023 05-024 05-025 05-026 05-027 ER-W3-2004-0615-000 ER-W3-2005-0145-000 ER-W3-2004-0276-001 ER-W3-2004-0276-002 ER-W3-2004-0122-000 ER-W3-2005-0378-000 ER-W3-2005-0396-000 ER-W3-2005-0334-001 ER-W3-2004-0331 -000 ER-W3-2000-0334-000 Supervisory System And Core Protection Calculator System Set-points Ultimate Heat Sink Impact Due To Extended Power Up-rate With Design Bases Tornado Event Annulus Negative Pressure Impact Due To Extended Power Up-Rate Considering Instrument Uncertainty Environmental Qualification Impacts Due To Alternate Source Term Methodology Steam Generator Tube Rupture Impacts Due To Alternate Source Term Methodology With Revised Assumptions Pressurizer Heater Sleeve And Instrument Nozzle Repair Outside Containment Leak Reduction Program Test Medium Change Confirmatory Criticality Calculation Correction For Spent Fuel Racks Temporary Alteration For Reactor Vessel Gasket Leak-off Pressure High Annunciator Reactor cavity cooling system temperature clarification Heating Ventilation And Air Conditioning Equipment Room And Component Cooling Heat Exchanger Room Calculations Correction