Letter Sequence Withdrawal |
---|
TAC:MD0197, Steam Generator Tube Integrity (Withdrawn, Closed) |
|
MONTHYEARML0606004582006-01-31031 January 2006 Westinghouse Electric Company LLC LTR-CDME-05-209-NP, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at the Wolf Creek Generating Station. Project stage: Request ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process Project stage: Request ML0609001572006-04-10010 April 2006 Withholding from Public Disclosure, LTR-CDME-05-209-P, MD0197 Project stage: Other ML0616500992006-06-27027 June 2006 Request for Additional Information (RAI) Related to License Amendment Request (LAR) to Revise the Steam Generator Program Project stage: RAI WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program Project stage: Response to RAI ML0716504002007-06-19019 June 2007 Notice of Meeting with Wolf Creek Nuclear Corp Regarding Nrc'S Request for Additional Information on 2/21/06 Licensee Amendment Request Re SG Tube Surveillance Program, Wolf Creek Generating Station Project stage: RAI ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation Project stage: Meeting ML0719802032007-08-0707 August 2007 Summary of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station to Discuss Second Request for Additional Information for Steam Generator Tube Surveillance Program LAR Project stage: RAI ML0722700022007-08-30030 August 2007 Topical Report, Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ET 07-0043, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-09-27027 September 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program Project stage: Response to RAI ML0730901272007-11-0808 November 2007 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss NRC Staff'S Request for Additional Information on Licensee'S Supplemental Letter to Letter Dated September 27, 2007, to Application Dated February 21, 2006 Project stage: RAI ML0732500032007-11-21021 November 2007 Memo to Thomas G. Hiltz Key Issues for Discussion for November 28, 2007 Meeting on Steam Generator Tube Inspection License Amendment (Tac MD0197) Project stage: Meeting ML0733004182007-11-29029 November 2007 Topical Report Withholding Information from Public Disclosure (Tac No. MD0197) Project stage: Other ML0733700452008-01-0404 January 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation Representatives Re Steam Generator Tube Surveillance Program Project stage: Meeting ML0803706102008-01-11011 January 2008 Westinghouse Electric Company LLC, LTR-CDME-08-2, Rev. 1 NP-Attachment, Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B*. Project stage: Request ML0804300062008-02-27027 February 2008 Request for Withholding Information from Public Disclosure, 01/11/2008 Affidavit Executed by J. A. Gresham, Westinghouse Electric Company LLC Project stage: Withholding Request Acceptance ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections Project stage: Withdrawal RS-08-047, Withdrawal of License Amendment Request Related Steam Generator Tube Alternate Repair Criteria2008-04-0101 April 2008 Withdrawal of License Amendment Request Related Steam Generator Tube Alternate Repair Criteria Project stage: Withdrawal 2007-06-19
[Table View] |
|
---|
Category:Federal Register Notice
MONTHYEARML24086A4312024-04-0505 April 2024 Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: April 16, 2024 ML24067A0372024-03-20020 March 2024 Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - February 2024 ML24018A0802024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd, and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Federal Register Notice) ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML21244A4282021-09-0909 September 2021 FRN - Notice of Issuance of COVID-19 Exemption Issued in August 2021 ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19207A4032019-07-26026 July 2019 FRN: General Notice. Confirmatory Order Issuance Wolf Creek Nuclear Operating Corporation ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 NRC-2017-0217, FRN Regarding Indirect Transfer of License (CAC No. MG0235; EPID L-2017-LLM-0005)2018-03-19019 March 2018 FRN Regarding Indirect Transfer of License (CAC No. MG0235; EPID L-2017-LLM-0005) ML18047A1732018-03-19019 March 2018 FRN Regarding Indirect Transfer of License (CAC No. MG0235; EPID L-2017-LLM-0005) ML17286A1802017-11-0808 November 2017 FRN - Notice of Consideration of Approval of Application Regarding Proposed Indirect License Transfer and Opportunity for a Hearing-FRN (CAC No. MG0235) EPID: L-2017-LLM-0005 ML17286A1572017-11-0808 November 2017 Letter - Notice of Consideration of Approval of Application Regarding Proposed Indirect License Transfer and Opportunity for a Hearing (CAC No. MG0235; EPID L-2017-LLM-0001) ML17248A2262017-09-15015 September 2017 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: October 3, 2017 ML17153A3782017-06-19019 June 2017 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: July 5, 2017 NRC-2017-0142, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: July 5,2017-06-19019 June 2017 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: July 5, 2017 ML17086A4272017-04-11011 April 2017 FRN Regarding Order Approving Indirect Transfer of Control of Renewed Facility Operating License NPF-42 ML16287A5862016-11-0808 November 2016 FRN, Acknowledgement of Application for Consent for Indirect Transfer of Control of License ML16287A5792016-11-0808 November 2016 Letter, Acknowledgement of Application for Consent for Indirect Transfer of Control of License ML16229A2552016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 NRC-2016-0180, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 20162016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20162016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16215A2272016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16179A4412016-08-0202 August 2016 FRN: Exemption, Issuance. Wolf Creek Generating Station Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16179A4402016-08-0202 August 2016 Letter, Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding NRC-2016-0162, FRN: Exemption, Issuance. Wolf Creek Generating Station Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding2016-08-0202 August 2016 FRN: Exemption, Issuance. Wolf Creek Generating Station Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML14254A0042014-09-12012 September 2014 Letter, Individual 14-Day Notice of Consideration of Issuance of Amendment, Revise Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Completion Time Extension (Exigent Circumstances) ML14233A2082014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 NRC-2014-0193, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 20142014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML14195A1222014-07-0303 July 2014 Federal Register Notice Withdrawing Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC Regulations. NRC-2014-0144, Federal Register Notice Withdrawing Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC Regulations.2014-07-0303 July 2014 Federal Register Notice Withdrawing Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC Regulations. ML14176A5202014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term NRC-2014-0054, FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term2014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14126A4382014-05-20020 May 2014 Facility Operating and Combined Licenses: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Acces ML12235A4032012-09-0505 September 2012 Notice of Withdrawal of Amendment Request Revision to Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology ML12235A3972012-09-0505 September 2012 LTR - Withdrawal of Amendment Request Revision to Technical Specification 5.6.5, Core Operating Limits Report (Corl) for Large Break Loss-of-Coolant Accident Analysis Methodology NRC-2012-0212, Notice of Withdrawal of Amendment Request Revision to Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology2012-09-0505 September 2012 Notice of Withdrawal of Amendment Request Revision to Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML1022501962010-08-20020 August 2010 Letter, Notice of Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating, for Note, Required Actions and Completion Times ML1022502062010-08-20020 August 2010 Notice of Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating, for Note, Required Actions and Completion Times ML1002502062010-02-26026 February 2010 Exemption from Requirements of 10 CFR Part 73 Implementation Deadline for Physical Security Plans ML1002501912010-02-26026 February 2010 Exemption from Requirements of 10 CFR Part 73 Implementation Deadline for Physical Security Plans NRC-2010-0032, Wolf Creek Generating Station - Exemption from Requirements of 10 CFR Part 73 Implementation Deadline for Physical Security Plans2010-02-26026 February 2010 Wolf Creek Generating Station - Exemption from Requirements of 10 CFR Part 73 Implementation Deadline for Physical Security Plans ML1001100992010-01-27027 January 2010 Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request ML0829507472008-11-20020 November 2008 Federal Register Notice for Wolf Creek Generating Station, Unit 1 Notice of Issuance of Renewed Facility Operating License No. NPF-42 for an Additional 20- Year Period ML0822506542008-08-18018 August 2008 Federal Register Notice - 555th Meeting of the Advisory Committee on Reactor Safeguards, September 4-6, 2008 2024-04-05
[Table view] Category:Letter
MONTHYEAR05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24036A0092024-02-14014 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0075 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 2024-09-06
[Table view] Category:Technical Specification
MONTHYEARML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23068A1232023-03-0909 March 2023 Changes to Technical Specification Bases Revisions 91 and 92 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22067A0302022-03-0808 March 2022 Changes to Technical Specification Bases - Revisions 86, 87, 88, 89, and 90 ML21070A0582021-03-11011 March 2021 Changes to Technical Specification Bases - Revisions 82, 83, 84, and 85 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20070L9822020-03-0202 March 2020 Changes to Technical Specification Bases - Revisions 80 and 81 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ML19078A1302019-03-11011 March 2019 Changes to Technical Specification Bases - Revisions 78 and 79 WO 19-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-03-11011 March 2019 Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18075A0242018-03-0808 March 2018 Changes to Technical Specification Bases - Revisions 76 and 77 WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ML17073A0932017-03-0909 March 2017 Changes to Technical Specification Bases - Revisions 74 and 75 ML17054C2212017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes ML17054C2202017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes ML16076A3572016-03-10010 March 2016 Changes to Technical Specification Bases - Revisions 67 Through 73 WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15077A0662015-03-11011 March 2015 Changes to Technical Specification Bases, Revisions 61 Through 66 WO 14-0092, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2014-12-15015 December 2014 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ET 13-0028, Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report.2013-09-23023 September 2013 Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report. ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML13079A0602013-03-0808 March 2013 Changes to Technical Specification Bases - Revisions 55 and 56 ML12080A2162012-03-12012 March 2012 Changes to Technical Specification Bases - Revisions 50 Through 54 WO 11-0086, Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating2011-11-30030 November 2011 Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 ML1007801282010-03-11011 March 2010 Changes to Technical Specification Bases - Revisions 41 Through 44 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report WO 09-0022, Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases2009-09-0303 September 2009 Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases ML0907506242009-03-11011 March 2009 Submittal of Changes to Technical Specification Bases - Revisions 36 Through 40 WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A2008-08-18018 August 2008 Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ML0811201492008-04-29029 April 2008 Corrected Technical Specification Pages, Amendment No. 177 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves, to Add Main Feedwater Regulating Valves and MFRV Bypass Valves ML0807805602008-03-0707 March 2008 Changes to Technical Specification Bases - Revisions 32 Through 35 ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707402282007-03-0909 March 2007 Changes to Technical Specification Bases - Revisions 24 Through 31 ML0631905352006-11-15015 November 2006 Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program 2024-08-14
[Table view] Category:Amendment
MONTHYEARML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ML16076A3572016-03-10010 March 2016 Changes to Technical Specification Bases - Revisions 67 Through 73 WO 11-0086, Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating2011-11-30030 November 2011 Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A2008-08-18018 August 2008 Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A ML0811201492008-04-29029 April 2008 Corrected Technical Specification Pages, Amendment No. 177 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves, to Add Main Feedwater Regulating Valves and MFRV Bypass Valves ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0631905352006-11-15015 November 2006 Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program ML0627804522006-10-0505 October 2006 Technical Specification Pages - Issuance of Amendment Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0624201502006-08-29029 August 2006 Techncial Specification, Addition of Surveillance Requirement 3.3.1.16 to TS Table 3.3.1.16 WO 06-0023, Revision to Technical Specification 3.5.2, ECCS - Operating.2006-06-0202 June 2006 Revision to Technical Specification 3.5.2, ECCS - Operating. ET 05-0001, Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program2005-04-18018 April 2005 Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program ML0507702972005-03-16016 March 2005 Tech Spec Page for Amendment 160 Revised Seal Injection Flow Rates ML0503301602005-01-31031 January 2005 Technical Specifications, Amendment 156 Plant Protection Test Times, Completion Times and Surveillance Test Intervals ML0503502612005-01-31031 January 2005 Tech Spec Pages for Amendment 158, Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports. WO 04-0050, Revision to Technical Specification (TS) 3.8.1, AC Sources-Operating, Diesel Generator Start Time Surveillance Requirements2004-12-13013 December 2004 Revision to Technical Specification (TS) 3.8.1, AC Sources-Operating, Diesel Generator Start Time Surveillance Requirements WO 04-0031, Revision to Technical Specification (TS) 5.3, Unit Staff Qualifications, and Corrections to Various TSs2004-10-0707 October 2004 Revision to Technical Specification (TS) 5.3, Unit Staff Qualifications, and Corrections to Various TSs WO 04-0027, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process2004-07-23023 July 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process WO 04-0035, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process2004-07-23023 July 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process WO 03-0057, Revision to Technical Specifications Regarding Extensions of AC Electrical Power Distribution Completion Time2003-10-30030 October 2003 Revision to Technical Specifications Regarding Extensions of AC Electrical Power Distribution Completion Time ML0221200382002-07-29029 July 2002 Technical Specifications for Amendment 123, Limited Removal of Suspension of Positive Reactivity Additions 2024-07-31
[Table view] |
Text
February 28, 2008 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - WITHDRAWAL OF LICENSE AMENDMENT REQUEST ON STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD0197)
Dear Mr. Muench:
By letter to the Nuclear Regulatory Commission (NRC) dated February 21, 2006 (ET 06-0004),
as supplemented by letters dated May 3 and September 27, 2007 (WO 07-0012 and ET 07-0043), and January 25, 2008 (ET 08-0006), you submitted a license amendment request (LAR) to revise Technical Specification (TS) 5.5.9, "Steam Generator (SG) Tube Surveillance Program," to exclude portions of the SG tube below the top of the tubesheet in the SGs from periodic tube inspections based on the application of structural analysis and leak rate evaluation results to re-define the primary-to-secondary pressure boundary. In addition, there were also proposed changes to add new reporting requirements to TS 5.6.10, Steam Generator Tube Inspection Report."
By letter dated February 14, 2008 (ET 08-0010), you have withdrawn the above request for a license amendment. This letter is to grant your request for withdrawal and provide you with a copy of the Notice of Withdrawal of Application for Amendment to Facility Operating License, which is enclosed and which will be forwarded to the Office of the Federal Register for publication. In your letter, you also requested that we provide you with the specific issues necessary to be resolved on the amendment request. The list of specific issues is provided in the second enclosure.
Sincerely,
/RA/
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Notice of Withdrawal
- 2. Specific Issues with Amendment That Need to be Resolved cc w/encls: See next page
ML080450185 OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CSGB/BC NRR/LPL4/BC NAME BSingal JBurkhardt AHiser THiltz DATE 2/25/08 2/19/08 2/26/08 2/28/08 Wolf Creek Generating Station (2/2006) cc:
Jay Silberg, Esq. Chief, Radiation and Asbestos Control Pillsbury Winthrop Shaw Pittman LLP Section 2300 N Street, NW Kansas Department of Health Washington, D.C. 20037 and Environment Bureau of Air and Radiation Regional Administrator, Region IV 1000 SW Jackson, Suite 310 U.S. Nuclear Regulatory Commission Topeka, KS 66612-1366 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation Senior Resident Inspector P.O. Box 411 U.S. Nuclear Regulatory Commission Burlington, KS 66839 P.O. Box 311 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation Chief Engineer, Utilities Division P.O. Box 411 Kansas Corporation Commission Burlington, KS 66839 1500 SW Arrowhead Road Topeka, KS 66604-4027 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant Office of the Governor 8201 NRC Road State of Kansas Steedman, MO 65077-1032 Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839
ENCLOSURE 1 NOTICE OF WITHDRAWAL OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 NOTICE OF WITHDRAWAL OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Wolf Creek Nuclear Operating Corporation (the licensee) to withdraw its application dated February 21, 2006, with supplemental letters dated May 3 and September 27, 2007, and January 25, 2008, for proposed amendment to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station, located in Coffey County, Kansas.
The proposed amendment would have revised Technical Specification (TS) 5.5.9, "Steam Generator (SG) Tube Surveillance Program," to exclude portions of the steam generator tube below the top of the tubesheet from periodic tube inspections based on the application of structural analysis and leak rate evaluation results to re-define the primary-to-secondary pressure boundary. In addition, there were also proposed changes to add new reporting requirements to TS 5.6.10, Steam Generator Tube Inspection Report."
The Commission had previously issued a Notice of Consideration of Issuance of Amendment, on the above proposed amendment application, that was published in the FEDERAL REGISTER on April 11, 2006 (71 FR 18377). However, by letter dated February 14, 2008, the licensee withdrew the proposed amendment.
For further details with respect to this action, see the application for amendment dated February 21, 2006, with supplemental letters dated May 3 and September 27, 2007, and
January 25, 2008, and the licensee's letter dated February 14, 2008, which withdrew the application for license amendment. Documents may be examined, and/or copied for a fee, at the NRC=s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management Systems (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737 or by email to pdr@nrc.gov.
Dated at Rockville, Maryland, this 28th day of February 2008.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ENCLOSURE 2 REMAINING TECHNICAL ISSUES RELATED TO TECHNICAL SPECIFICATION AMENDMENT REQUEST REGARDING STEAM GENERATOR TUBE INSPECTIONS BASED ON H*/B* METHODOLOGY TAC NO. MD0197 WOLF CREEK GENERATING STATION DOCKET NO. 50-482
REMAINING TECHNICAL ISSUES RELATED TO TECHNICAL SPECIFICATION AMENDMENT REQUEST REGARDING STEAM GENERATOR TUBE INSPECTIONS BASED ON H*/B* METHODOLOGY TAC NO. MD0197 WOLF CREEK GENERATING STATION DOCKET NO. 50-482
References:
- 1. Westinghouse report WCAP-16932-P (Proprietary), Revision 1 (Agencywide Access and Management System (ADAMS) Accession No. ML031910141), Appendix B, Tube-to-Tubesheet Joint Strength Analysis, May 2003.
- 2. Wolf Creek Nuclear Operating Corporation (WCNOC) letter dated February 21, 2006 (ADAMS Accession No. ML060600454), which requested an amendment to the Technical Specifications (TS) for H*/B* and which included a technical support document.
- 3. WCNOC letter dated May 3, 2007 (ADAMS Accession No. ML071290101), which provided a response to an NRC Request for Additional Information (RAI) dated June 27, 2006, and which also provided a revised amendment request for H*/B*.
- 4. WCNOC letter dated September 27, 2007 (ADAMS Accession No. ML072750610),
which provided a response to an NRC Request for Additional Information (RAI) provided at a July 11, 2007, meeting with WCNOC (see NRC ADAMS Accession No. ML071980203 for meeting summary) and which provided a revised amendment request for H*/B*.
- 5. Summary of meeting with WCNOC representatives on November 28, 2007 regarding steam generator tube surveillance program (NRC ADAMS Accession No. ML073370045).
Information That Needs to be Provided to the Staff:
The U. S. Nuclear Regulatory Commission (NRC) staffs review of the proposed amendment was intended to ensure that all of the tubes in the Steam Generator (SG) have adequate structural integrity and that the SG has adequate leakage integrity. In reviewing the licensees analysis supporting its amendment request, the NRC staff determined that the licensee had not provided the information below which is necessary to support a conclusion that the tubes would have adequate integrity if flaws were to occur in the region of the tube not inspected.
- The licensee must adequately demonstrate that the proposed H*/B* distances make adequate allowance for uncertainties such as to ensure with a high probability (e.g., 0.99) that all 22,500 tubes at Wolf Creek Generating Station (WCGS) will exhibit pullout resistances consistent with the TS performance criteria. The licensees stacked uncertainty model does not conservatively bound the uncertainties for an individual tube. The licensees discussion of extreme
value considerations lacks completeness, not considering certain key variables and combinations of variables.
- The licensee must provide sufficient information to adequately characterize the potential range in values of residual contact pressure between the tube and tubesheet (due to the hydraulic expansion process) which may be encountered among the 22,500 tubes at WCGS. Only limited pullout data exists upon which the residual contact pressures are estimated. The data exhibits significant scatter. Residual contact pressure (and thus residual pullout load capacity) is highly sensitive to several parameters, including hydraulic expansion pressure, tube yield strength, tube material strain hardening properties, and initial radial gap (i.e., pre-expansion) between the tube and tubesheet. The licensee has not provided information to establish whether the pullout test specimens adequately envelop the range of values of these parameters which may be encountered in the WCGS SGs.
- The licensee must provide sufficient information (e.g., literature search for relevant data, expert opinion and experience) to adequately characterize the range in potential values of the thermal expansion coefficient (TEC) for the tubesheet material and tube material which may be encountered in the field. In addition, the licensee has not provided sufficient information concerning potential changes to the tube material TEC due to the hydraulic expansion process (i.e.,
due to cold working).
- The licensees analysis must sufficiently demonstrate that incremental slippage of the tubing under cyclic operational loads will not occur, or compensatory monitoring for slippage should be proposed.
- The method for accounting for the pressure in the crevice between the tube and tubesheet (i.e., limiting median crevice pressure model) must be demonstrated to be conservative for all conditions (e.g., normal operating conditions and steam line break) and for all tubes within the tubesheet.
- At the meeting on December 13, 2007, the licensee identified the use of a beta factor which is embedded in the crevice pressure model for at least some of the H*/B* analyses and which may have a significant influence on the H*/B*
distances. This beta factor was only briefly discussed during the meeting, but apparently may significantly influence some of the H*/B* analyses. The use of this beta factor, its purpose, and its technical basis must be submitted for NRC review.
- During the December 13, 2007, meeting, the licensee also stated that the method used to scale the results of tubesheet finite element analyses from normal operating conditions to steam line break conditions was inappropriate, leading to over-conservative results for steam line break. The nature of the problem and the resolution must be submitted for NRC review.
The following items are the specific issues that the NRC staff had outstanding when the WCGS amendment was withdrawn:
- 1. This question does not need to be responded to if the theory of elasticity model in Reference 4, Enclosure I, page 7, is not used in the H*/B* analyses.
Reference 4, Enclosure I, page 7, states that the F/L value in Reference 2, Enclosure I, Table 6-4, is correct based on the theory of elasticity model. However, the supporting discussion for this statement appears to contain inconsistencies and appears to be inconsistent with the original development of this model in Reference 1. Specifically, the theory of elasticity model presented in the middle of page 7 of Enclosure I to Reference 4 is described on page 8 (second to last paragraph) as being applicable to a linear distribution of initial contact pressure through the thickness of the tubesheet (over the length L). However, it is the staffs understanding, based on its review of Reference 1, that this model was actually developed assuming an initial contact pressure (P0) from the hydraulic expansion which is constant through the thickness of the tubesheet (over the length L). Also, the NRC staff notes that the above F/L value was determined from Equation 3 on page 8 as a function of the term Pc whose value was assumed equal to P0 as determined from the theory of elasticity. The NRC staff believes this approach leads to an incorrect value of F/L since the contact pressure will only equal P0 at a distance L from the top of the tubesheet, decreasing to ever smaller values at decreasing distances from the top of the tubesheet. The NRC staff also notes that the stated F/L value suggests that the smallest length test specimen is capable of resisting total axial force, which is substantially higher than the test data indicates. The staff's concerns described above, including a complete description of why the stated F/L value is correct, need to be addressed.
- 2. Reference 4, Enclosure I, page 9 - The contact pressures and F/L values are based on the first principle approach such that they represent average values over the length of the test specimens. Based on the theory of elasticity equation discussed in item 1 above, pullout force is not expected to be linear with the length of the specimen. Thus, it appears to NRC staff that the listed contact pressures and F/L values for the smallest length specimens are not directly comparable to those for the longer specimens for purposes of calculating mean and mean minus 1 sigma values. The NRC staff has the same concern about the pullout data for the Model D5 and 44F specimens. The listed contact pressures and F/L values are only conservative for H*/B* distances less than the length the test specimens. For Model F, the listed contact pressures and F/L values for the smallest length specimens are not conservative if assumed to apply to H*/B*
distances greater than that length. (This concern is much more urgent in the case of Model D5 and 44F since the test specimens for these models were substantially shorter)
The staffs concerns discussed above need to be addressed including whether there is a need to adjust the pullout data such as to produce mean and mean minus 1 sigma estimates of contact pressure and F/L that are conservative for the range of H*/B* values that may ultimately be proposed.
- 3. Reference 4, Enclosure I, page 9 - The listed pull forces are described as corresponding to a 0.25 inch displacement. In Reference 2, Enclosure I, Table 6-3, these same pull forces are described as being the maximum value recorded. Table 6-4 implies that the pull force data are smaller for 0.25 inch displacements. Which data are correct? What are the pull force values for tests 1 though 8 corresponding to 0.25 inch displacements?
- 4. Reference 3, Enclosure 1, Table 1, provided test specimen dimensions for specimens 33625-09 to 33625-33625-15. Since the H*/B* analysis is now being based on pull test results for other specimens, a similar dimensional data for these other specimens (i.e.,
R12C08, R11C08, R12C07, R11C07, R10C08, R10C07) is needed. Also, the yield strength for each of the eight specimens in Table 1 is also needed.
- 5. Reference 4, Enclosure I, page 9 - The yield strength for each of the eight specimens in the table are needed.
- 6. Reference 4, Enclosure I, page 9 - Apart from the scaling issues discussed in Question 2 above, the adequacy of the data set in the Table to address the range of potential values of the key variables affecting the residual contact pressure and F/L values which may be found in the field among the population of 22500 tubes needs to be addressed. Based on the responses to questions 4 and 5 above, what adjustments to the mean and mean minus 1 sigma values of contact pressure and F/L are needed to reflect the full range of all key variables. The NRC staff notes that the spider chart (Figure 2 of Reference 3, Enclosure I) provides a potential tool for making such adjustments.
- 7. Reference 4, Enclosure I, page 16 - The report states that certain parameters were not directly evaluated as part of the H*/B* sensitivity study. In Table 2-1 on page 19 of the report, the residual contact pressure uncertainty is assumed to be a function of only yield strength and Youngs Modulus uncertainties. However, the spider chart in Figure 2 of Reference 3 shows that the residual contact pressure associated with the hydraulic expansion process is highly sensitive to certain variables. For this reason, the response to question 6 above should address hydraulic expansion pressure, strain hardening, and initial tube to tubesheet radial clearance as potential key variables affecting residual contact pressure.
- 8. Reference 4, Enclosure I, pages 10 and 11 - The pull test data for Model D5 and 44F exhibit considerably more scatter (even in terms of P0 as determined from the theory of elasticity equation discussed in Question 1) than the Model F data on page 9. An explanation of the Model F data with that for Model D5 and 44F is needed. Whether the data values and scatter are consistent among the models when the data are adjusted to reflect the full range of all the key input parameters affecting the pullout resistance needs to be addressed.
- 9. Reference 4, Enclosure I, page 13, bottom of page - Its not clear to the NRC staff where the mean minus 1 sigma value of residual contact pressure from hydraulic expansion comes from. The cited reference (Reference 3, Enclosure I, Figure 2) is the spider chart which doesnt address this value. Also, this value is slightly inconsistent with the value shown in the Table in Reference 4, Enclosure I. Explain this apparent discrepancy.
- 10. Reference 4, Enclosure I, page 18 - The report considered two different nominal values of thermal expansion coefficient (TEC) for alloy 600 tubing and two different nominal values for the A508 tubesheets. The nominal TEC values are based on (1) nominal ASME Code values for both the tube and tubesheet and (2) data from ANTER Laboratories Inc. for both the tube and tubesheet. TEC variability relative to these nominal values was assumed to have a standard deviation of 1.5% based on reported measurement uncertainty associated with the ANTER data. However, the report provided no evidence that either TEC model (i.e., that based on Code values versus that based on the ANTER data) captures the range of TEC values that may be encountered in the field. In addition, recent TEC data from PMIC indicate smaller TEC differences between the tube and tubesheet materials than is indicated by either of the above TEC models, thus adding to the staffs concern as whether either TEC model captures the range of TEC values which may exist in the field. A more complete technical justification for the TEC model is needed in terms of its ability to capture the range of TEC differences between the tube and tubesheet that may be encountered in the field. This technical justification should address, but not necessarily be limited to the following:
- a. Literature search for relevant TEC data, and evaluation of that data. If the PMIC data is considered not relevant, what is the basis? Apart from the American Society of Mechanical Engineers (ASME) Code vetting process, is there any reason to believe that the pedigree of the PMIC data (or ANTER data) is not as good as the data upon which the Code values are based? What is the feasibility of subjecting the PMIC and ANTER data to a review similar to that performed as part of the Code vetting process?
- b. Expert opinion and experience on the variability of TEC that may be exhibited by materials such as alloy 600 and A508 steel that may have fabricated from different heats of material, at different times, and with different processing histories (e.g., mill annealed versus thermally treated alloy 600, temperatures experienced during post weld heat relief).
- c. Expert opinion and experience on potential changes to alloy 600 TEC due to hydraulic expansion process. Data concerning sensitivity of TEC to cold working for metals in general needs to be provided.
- 11. Reference 4, Enclosure I, page 19 - The report states that the probability that the stacked model H*/B* will not meet the performance criteria of NEI 97-06, Rev. 2 is 2.6E-06 which is orders of magnitude less than the acceptance criteria which is a probability of 0.01.
This appears to the NRC staff to be a misstatement. The staffs review of the stacked model analysis in Table 2-1 indicates that the 2.6E-06 probability number applies to each individual tube, not to the population of 22,500 tubes at Wolf Creek. Given that the H*/B*
distance of each individual tube has a certain probability (e.g., 2.6E-06) of not meeting the performance criteria, it must be verified that that the probability that one or more tubes out of a population of 22,500 tubes will fail to meet the performance criteria is less than 0.01. Alternatively, an acceptance criterion applicable to the probability of not meeting the performance criteria of each individual tube must be developed consistent with the overall goal of ensuring that the probability that one or more tubes out of a population of 22,500 tubes will fail to meet the performance criteria is less than 0.01.
Revisions to the acceptance criteria approach, or an explanation why the approach in the report is correct, is needed.
- 12. Reference 4, Enclosure I, page 19 - The stacked uncertainty analysis in Table 2-1 considers each of six parameters be at their mean + 1 sigma value (+ or - depending on which is more conservative) with one exception, tubesheet hole/tube dimension. This parameter was considered at the mean + 2 sigma value. These mean + X sigma values were the values used in the reference H*/B* analyses shown in Tables 2-2 and 2-3 of the report. The probability that all six of these parameters could be at or outside these mean
+ 1 sigma values is 2.6E-06. The NRC staff is concerned that this does not provide a conservative representation of the limiting H*/B* distance. The approach assumes that the H*/B* distances are equally sensitive to all six input parameters. Independent NRC staff calculations, discussed at December 13, 2007 meeting, shows that the H*/B*
distances are strongly sensitive to residual contact pressure associated with hydraulic expansion (which in turn was considered to be a function of yield strength), tube TEC, and tubesheet TEC, but to be only weakly sensitive to Youngs Modulus for the tube and tubesheet, respectively, and the tubesheet hole/tube dimension. To ensure a conservative analysis, a robust extreme value uncertainty analysis is needed. Such an analysis should focus on those parameters which dominate the H*/B* uncertainties (e.g.,
residual contact pressure, tube TEC, and tubesheet TEC), both individually and in various combinations. Alternatively, a comprehensive Monte Carlo analysis of the probability density functions of all input parameters affecting H*/B* may be submitted in lieu of an extreme value analysis. [The NRC staff acknowledges that pages 24 and 25 of the report do touch on extreme value considerations. However, this treatment is not complete. For example, a 5 sigma variation on yield strength reducing residual pressure to essentially zero is discussed, but equally realistic cases such as 2 sigma variations on residual contact pressure, tube TEC, and tubesheet TEC, or 3 sigma variations on tube TEC and tubesheet TEC are not discussed. In addition, a robust extreme value analysis should reflect the responses to questions above dealing with residual contact pressure and tube and tubesheet TECs.]
- 13. Reference 4, Enclosure I, pages 19 and 20 - The report addresses the uncertainties on the degree of constraint provided by the divider plate on tubesheet vertical deflection.
However, for a given divider plate assumption, the report does not address the accuracy of the finite element analyses in terms of how they affect tubesheet hole dilation, resulting increase or decrease in tube to tubesheet contact pressure, and the H*/B*
distances. (For example, finite element Model O-1 is an axisymmetric model to which a divider plate factor (from 3-D model analysis) is applied. The tubesheet and its boundary conditions (including the divider plate connection) are not truly axisymmetric.) Discuss the significance of the finite element accuracy on calculated tubesheet hole dilation, resulting increase or decrease in tube to tubesheet contact pressure, and the H*/B*
distances and, in light this significance, how is the conservatism of the H*/B* distances is being assured.
- 14. At the meeting on December 13, 2007, the licensees contractor, Westinghouse, stated that it had discovered an error in the way the unit load finite element analyses were being combined which led to over-conservative results for steam line break. A description of the error, which was found and how it was corrected, is needed.
- 15. The variability of some input parameters such as tube yield strength or tube expansion pressure may vary somewhat randomly from tube to tube whereas other input parameters, particularly those associated with the tubesheet, may have a more systematic variation from a nominal value. Discuss how this affects the implementation of the uncertainty analyses being employed in support of the proposed H*/B* distances.
- 16. Reference 4, Enclosure I, pages 34 and 39 - As discussed at the meeting with the licensee on November 28, 2007 (Reference 5), these pages of the report and information presented at the meeting do not provide sufficient evidence that incremental slippage of the tubing within the tubesheet will not occur under heatup/cooldown and other operational loading cycles. Potential monitoring strategies were discussed at the meeting. A description of any changes to the previously proposed technical specification amendment request that define the necessary monitoring program is needed.
- 17. Reference 4, Enclosure I, page 40 - The report lists the accidents for which primary to secondary leakage is modeled in the Wolf Creek Update Final Safety Analysis Report (USAR). Feed line break is not included in the list, presumably because a qualitative comparison with steam line break was performed in accordance with NUREG-800, Standard Review Plan, and it determined feed line break to be less limiting from a radiological consequence standpoint. Is the previous finding in the USAR that steam line break is most limiting still valid in the context of the B* analysis and, if yes, why? If not, how will this situation be remedied? [Basis for question: The NRC staff notes that the key variables affecting the relative flow resistance in the tube to tubesheet crevice between steam line break and normal operating conditions are viscosity and the effective crevice length, since loss coefficient is now assumed to be constant with increasing positive contact pressure. While there is a significant viscosity difference between steam line break temperatures and normal operating temperatures, there is only a small viscosity difference between feed line break temperatures and normal operating temperatures. Thus, B* distances for feed line break would tend to be larger for feed line break than steam line break.]
- 18. Reference 4, Enclosure I, pages 66 to 71 - These pages address, in part, the conservatism of the limiting median crevice pressure approach for modeling the pressure within the crevice. As discussed at the meetings with the licensee on November 28 and December 13, 2007, the NRC staff has performed independent calculations using a more realistic distribution of crevice pressure as a function of elevation roughly based on the results of the Westinghouse crevice test results. The staffs calculations indicated that the limiting median crevice pressure approach leads to non-conservative H*/B* predictions at certain radial locations including the most limiting locations. What is needed is to incorporate realistic crevice pressure assumptions, based on the test data, to verify the conservatism of the limiting median crevice pressure approach or, if not conservative at all locations, to update its H*/B* calculations to reflect realistic or conservative crevice pressure distributions. Details of the analysis should be provided.
- 19. At the meeting on December 13, 2007, Westinghouse identified the use of a beta factor which is embedded in at least some of the H*/B* analyses. As the NRC staff understands the explanation at the meeting, this beta factor has been used to adjust the crevice pressure to define an effective crevice pressure acting on the inside surfaces of
the tubesheet holes. It is the staffs understanding that the beta factor is intended to account for the fact that radial displacement of the surface of the tubesheet holes is governed not just by the crevice pressure within the tubesheet hole in question but by crevice pressures acting on nearby tubesheet holes. The staffs understanding of the "beta factor" needs to be addressed. A detailed description of how the beta factor was developed and how it is used in the development of the proposed H*/B* distances need to be provided. The NRC staff notes that the crevice pressures may vary significantly among the tubesheet holes depending on whether or not the tubes contain through wall cracks or whether or not they are completely severed. For example, the tubesheet hole in question may contain a fully severed tube. The adjacent tube holes may contain tubes with no cracks and thus with an entirely different crevice pressure than the tubesheet hole in question. Thus, the description of the development of the beta factor needs to explain how the beta factor is affected by the spectrum of possibilities regarding the crevices pressures in neighboring tube holes.
- 20. An updated set of Figures and Tables (similar to those in Reference 2) describing the results of the H* and B* analyses and all accompanying input parameters (including crevice pressure and beta factor assumptions) needs to be provided. This is needed for the cases (1) where the stub runner to divider plate weld is 100% degraded and (2) where the divider plate is fully effective in restricting tubesheet vertical deflection.