ML112510319

Waterford Steam Electric Station, Unit 3 - Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report (TAC No. ME1359)

ML112510319
Person / Time
Site:	Waterford
Issue date:	09/20/2011
From:	Kalyanam N Plant Licensing Branch IV
To:	Entergy Operations
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC ME1359
Download: ML112510319 (6)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 20, 2011 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 -CORRECTION OF AN ERROR IN AMENDMENT NO. 226 REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 6.6.5, CORE OPERATING LIMITS REPORT (TAC NO. ME1359) Dear Sir or Madam: On May 25, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 101340109), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 226 to Facility Operating License No. NPF-38 for Waterford Steam Electric Station, Unit 3 (Waterford 3), in response to Entergy Operation, Inc.'s (the licensee's) application dated May 22,2009, as supplemented by letter dated May 17,2010 (ADAMS Accession Nos. ML091470271 and ML 101400028, respectively). The application proposed a change to Technical Specification (TS) 6.9.1.11, to minimize the number of references consistent with the guidance provided in NRC Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications". By letter dated July 26, 2010 (ADAMS Accession No. ML 102100200), Entergy identified the Limiting Condition of Operation for Moderator Temperature Coefficient in the TSs, 3.1.1.3, was incorrectly identified as 3.1.1.4 in its letters dated May 22, 2009, and May 17, 2010, and the administrative error was editorial in nature and only affected a portion of the TS pages and did not exist in any of the letter material content of the safety evaluation. Additionally, the licensee stated that the administrative error does not change any of the information that was submitted to the NRC and that the cover letter and safety evaluation for Amendment No. 226 did not contain this error. Entergy also stated that error was a "copy and paste" problem from the Arkansas Nuclear One (ANO) specification to the Waterford 3 specification.

-2 Thus, according to the NRC's policy established by SECY-96-238, "Proposed Guidance For Correction of Technical Specification Typographical Errors," dated December 17,2006 (ADAMS Accession No. ML003754054), this error can be corrected by a letter. Enclosed please find the replacement TS pages 6-20 and 6-20a. This correction does not change any of the conclusions in the safety evaluation associated with the amendment. Sincerely, N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 Enclosure: As stated cc w/encl: Distribution via Listserv REVISED TECHNICAL SPECIFICATION FOR AMENDMENT NO. 226 ISSUED ON MAY 25, WATERFORD STEAM ELECTRIC STATION, UNIT INDUSTRIAL SURVEY OF TOXIC OR HAZARDOUS CHEMICALS REPORT 6.9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years. 6.9.1.10 A survey of major pipelines ( .:: 4 inches) within a 2-mile radius of Waterford 3, which contain explosive or flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years. CORE OPERATING LIMITS REPORT COlR 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle or any remaining part of a reload cycle for the following: 3.1.1.1 SHUTDOWN MARGIN -ANY CEA WITHDRAWN 3.1.1.2 SHUTDOWN MARGIN -All CEAS FUllY INSERTED 3.1.1.3 MODERATOR TEMPERATURE COEFFICIENT 3.1.2.9 BORON DilUTION 3.1.3.1 CEA POSITION 3.1.3.6 REGULATING AND GROUP P CEA INSERTION LIMITS 3.2.1 LINEAR HEAT RATE 3.2.3 AZIMUTHAL POWER TilT -Tq 3.2.4 DNBR MARGIN 3.2.7 AXIAL SHAPE INDEX 3.6.1.5 AIR TEMPERATURE, CONTAINMENT (linear Heat Rate, 3.2.1) 3.9.1 BORON CONCENTRATION 6.9.1.11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC as follows: "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores" (WCAP-11596-P-A), "ANC: A Westinghouse Advanced Nodal Computer Code" (WCAP-10965-P-A), and "ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery" (WCAP-10965-P-A Addendum 1) (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion limits, 3.2.4.b for DNBR Margin, 3.1.2.9 for Boron Dilution, and 3.9.1 for Boron Concentrations) . "CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A (Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion limits and 3.2.3 for Azimuthal Power Tilt). WATERFORD -UNIT 3 6-20 AMENDMENT NO. 68,102,158, 182, 191 226 Corrected by letter dated 91;20/2011 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT COLR (Continued) "Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A (Methodology for Specification 3.2.4.c and 3.2.4.d for DNBR Margin and 3.2.7 for ASI). "Calculative Methods for the CE Large Break LOCA Evaluation Model," P (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI). "Calculative Methods for the CE Small Break LOCA Evaluation Model," P (Methodology for SpeCification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI). "Technical Manual for the CENTS Code," WCAP-15996-P-A, Rev. 1 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.3 for MTC, 3.1.3.1 for CEA Position, 3.1.3.6 for Regulating and Group P Insertion Limits, and 3.2.4.b for DNBR Margin). "Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI). "Qualification of the Two-Dimensional Transport Code PARAGON," A (may be used as a replacement for the PHOENIX-P lattice code as the methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, 3.2.4.b for DNBR Margin, 3.1.2.9 for Boron Dilution, and 3.9.1 for Boron Concentrations). "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," WCAP-16072-P-A (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Tilt, and 3.2.7 for ASI). 10) "CE 16 x 16 Next Generation Fuel Core Reference Report," WCAP-16500-P-A (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI). 11} "Optimized ZIRLOŽ, WCAP-12610-P-A and CENPD-404-P-A Addendum 1-A {Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI}. 12) "Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes," WCAP-16523-P-A (Methodology for Specification 3.2.4.b, 3.2.4.c and 3.2.4.d for DNBR Margin). 13) "ABB Critical Heat Flux Correlations for PWR Fuel," CENPD-387 -P-A (Methodology for Specification 3.2.4.b, 3.2.4.c and 3.2.4.d for DNBR Margin and 3.2.7 for ASI). AMENDMENT NO. 102, 146, 168, WATERFORD -UNIT 3 6-20a 182,188,191,200,210,214,226 Corrected by letter dated 9/20 12011 Thus, according to the NRC's policy established by SECY-96-238, "Proposed Guidance For Correction of Technical Specification Typographical Errors," dated December 17, 2006 (ADAMS Accession No. ML003754054), this error can be corrected by a letter. Enclosed please find the replacement TS pages 6-20 and 6-20a. This correction does not change any of the conclusions in the safety evaluation associated with the amendment. Sincerely, IRAI N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 Enclosure: As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMWaterford Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource RecordsAmend Resource GHill,OIS ADAMS Accession No. ML 112510319 OFFICE DORLlLPL4/PM DORLlLPL4/LA DORLlLPL4/BC "'******** " .......... 'C ....."_._"'*** DORLlLPL4/PM ** NAME NKalyanam JBurkhardt MMarkley NKalyanam II DATE 9/16/11 9/16/11 9/20/11 __-.""'= ,. --9/20/11 -...OFFICIAL RECORD COpy