W3F1-2006-0012, Report of Facility Changes, Tests and Experiments and Commitment Changes

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

Entergy Nuclear South Entergy Operations. Inc.

17265 River Road Killona, LA 70057-3093 "ftergy 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

Attachment 1 W3Fl -2006-0012 Waterford 3 10 CFR 50.59 Summary Report to W3F1-2006-0012 Page 1 of 2 1OC:FR50.59 Initiating Summary Evaluation Document Number 04-C004 Amendment 91 New TRM 3.0/4.0 Section, Remove Shutdown Requirements From TRM 04-005 Amendment 92 Move Pressurizer Heat-up and Cooldown Limits to TRM and Remove Shutdown Requirements 04-C007 Calculations EC-M88-021 Station Blackout Water Requirements From and EC-E89-016 Extended Power Up-rate 04-C008 ER-W3-2001-1149-005 Extended Power Up-rate Impact To FSAR Chapter 5 04-C009 ER-W3-2001-1149-01 0 Extended Power Up-rate Impact To FSAR Chapter 10 05-001 ER-W3-2004-1129-015 Extended Power Up-rate Impact To FSAR Chapter 15 05-C'02 ER-W3-2001-1149-009 Extended Power Up-rate Impact To FSAR Chapter 9 05-C003 ER-W3-2004-01 37-000 In Core Instrumentation Thimble Support Plate Modification 05-C104 ER-W3-2004-0276-000 Alternate Source Term Implementation 05-C005 ER-W3-2004-0478-000 Steam Generator Sub-compartment Platforms Addition Impact 05-C106 ER-W3-2004-0602-000 Steam Generator Feedwater Pump Trip Logic Modification Due To Extended Power Up-rate 05-C107 ER-W3-2004-01 22-000 Pressurizer Heater Sleeves And Instrument Nozzles Weld Repair 05-C108 ER-W3-2005-001 9-000 Steam Generator Level Set-points Modification Due To Extended Power Up-rate 05-C109 ER-W3-2003-0662-000 480 Volt Safety Buses Limit Change When On Startup Transformers 05-01 1 ER-W3-2005-0083-000 Health Physics Calculations Implementation From Extended Power Up-rate And Alternate Source Term 05-C1 2 ER-W3-2004-01 16-003 Core Next Generation Fuel And Lead Test Assemblies From Reload Analysis Report 05-01 3 ER-W3-2003-0053-000 High Pressure Turbine Design Upgrade For Extended Power Up-rate 05-C1 4 ER-W3-2002-0595-000 Main Generator Output Breaker Modification From Extended Power Up-rate 05-015 ER-W3-2005-01 30-000 Temporary Alteration For Keeping Circulating Water System Operating 05-C1 6 License Amendment Technical Requirements Manual and Final Request NPF 38-249 Safety Analysis Report change due to Extended Power Up-rate 05-017 Core Operating Limits Changes To Moderator Temperature Report and Startup and Coefficient, Linear Heat Rate, Departure From Setpoint Transmittal for Nuclear Boiling Rate Margin, Axial Shape Cycle 14 Index; Revised Core Operating Limit to W3F1 -2006-0012 Page 2 of 2 Supervisory System And Core Protection Calculator System Set-points05-018 ER-W3-2004-0615-000 Ultimate Heat Sink Impact Due To Extended Power Up-rate With Design Bases Tornado Event 05-019 ER-W3-2005-0145-000 Annulus Negative Pressure Impact Due To Extended Power Up-Rate Considering Instrument Uncertainty 05-020 ER-W3-2004-0276-001 Environmental Qualification Impacts Due To Alternate Source Term Methodology 05-021 ER-W3-2004-0276-002 Steam Generator Tube Rupture Impacts Due To Alternate Source Term Methodology With Revised Assumptions05-022 ER-W3-2004-0122-000 Pressurizer Heater Sleeve And Instrument Nozzle Repair 05-023 ER-W3-2005-0378-000 Outside Containment Leak Reduction Program Test Medium Change 05-024 ER-W3-2005-0396-000 Confirmatory Criticality Calculation Correction For Spent Fuel Racks05-025 ER-W3-2005-0334-001 Temporary Alteration For Reactor Vessel Gasket Leak-off Pressure High Annunciator 05-026 ER-W3-2004-0331 -000 Reactor cavity cooling system temperature clarification 05-027 ER-W3-2000-0334-000 Heating Ventilation And Air Conditioning Equipment Room And Component Cooling Heat Exchanger Room Calculations Correction