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MONTHYEARW3F1-2009-0017, License Amendment Request NPF-38-281 to Revise Technical Specification 6.9.1.11, Core Operating Limits Report2009-05-22022 May 2009 License Amendment Request NPF-38-281 to Revise Technical Specification 6.9.1.11, Core Operating Limits Report Project stage: Request ML0916301512009-06-12012 June 2009 Acceptance Review Email, License Amendment Request, Revise Technical Specification 6.9.1.11, Core Operating Limits Report to Add New Analytical Methods to Support Implementation of Westinghouse Next Generation Fuel Project stage: Acceptance Review ML0925201242009-09-17017 September 2009 Request for Additional Information, License Amendment Request, Revise TS 6.9.1.11, Core Operating Limits Report to Add New Analytical Methods to Support Implementation of Westinghouse Next Generation Fuel Project stage: RAI 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References Project stage: Response to RAI ML1013401092010-05-25025 May 2010 Issuance of Amendment No. 226, Administrative Changes to Technical Specification 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report Project stage: Approval ML1125100612011-09-0808 September 2011 Licensee Email UFSAR Clarification Project stage: Other ML1125103192011-09-20020 September 2011 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 Project stage: Other 2010-05-17
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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis ML21116A1432021-04-26026 April 2021 (Waterford 3) - Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. ML1125103192011-09-20020 September 2011 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 ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System.2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System. 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program ML1005504632010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0711603482007-04-24024 April 2007 License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding ML0706803372007-03-19019 March 2007 Tech Spec Pages for Amendment 212 Reactor Coolant System Leakage Detection Instrumentation ML0703704312007-02-0606 February 2007 Technical Specifications, Issuance of Amendment No. 211 to Facility Operating License Removal of Vendor Recommended Diesel Generator Surveillance Requirement 2023-07-26
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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. ML101340109), 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 ML101400028, 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. ML102100200), 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:
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