Letter Sequence Meeting |
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TAC:MD0197, Steam Generator Tube Integrity (Withdrawn, Closed) |
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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
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Category:Memoranda
MONTHYEARML24297A6392024-10-30030 October 2024 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML24268A0722024-09-24024 September 2024 Summary of August 28, 2024, Public Meeting to Discuss Cyber Security Regulatory Issues Regarding Wolf Creeks Implementation of Advanced Remote Monitoring Using Wireless ML23179A2132023-07-0505 July 2023 Approval for Credit for the Wolf Creek Generating Station Operational Safety Review Team to the Baseline Inspection Samples/Hours ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21309A5482021-11-15015 November 2021 NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation ML21243A4492021-09-0202 September 2021 ISFSI Technical Assistance Request - Review of Physical Security Plan ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML17019A2912017-01-19019 January 2017 Notice of Closed Regulatory Conference with Wolf Creek Generating Station ML17019A2932017-01-19019 January 2017 Notice of Closed Regulatory Conference with Wolf Creek Generating Station ML16064A1872016-03-0404 March 2016 Closed Pre-Decisional Enforcement Conference with Wolf Creek Nuclear Operating Corporation ML15251A0092015-09-11011 September 2015 Review of Revision 28 to the Updated Safety Analysis Report ML15015A1712015-01-0808 January 2015 Focused Baseline Inspection at the Wolf Creek Site for a Major Essential Service Water Modification ML14197A3442014-07-25025 July 2014 Review of Revision 27 to the Updated Safety Analysis Report ML13204A2432013-07-24024 July 2013 Notice of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13109A2342013-07-12012 July 2013 Safety Evaluation Regarding Wolf Creek Generating Station - Loss of Offsite Power and Augmented Inspection, Issue for Resolution 2012-004 ML13179A1012013-07-0909 July 2013 7/30/13 Notice of Forthcoming Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station ML13093A0592013-04-0202 April 2013 Public Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Performance Assessment Results for Wolf Creek Generating Station for 2012 ML13078A1552013-03-20020 March 2013 License Amendment Request to Change Diesel Generator Surveillance Requirements ML12249A0292012-09-0606 September 2012 9/20/12 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Wolf Creek Station ML1222602142012-08-16016 August 2012 Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event ML12011A1012012-01-19019 January 2012 Summary of Meeting with NEI and to Address Di&C Issues ML1101106702011-02-0707 February 2011 Fire Protection Safety Evaluation Input for Wolf Creek Generating Station Regarding License Amendment Request for Deviation from the Fire Protection Program Requirements ML1006010322010-03-0101 March 2010 Cy 2009 Baseline Inspection Completion ML0929300152009-10-20020 October 2009 Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 ML0928003162009-10-16016 October 2009 Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively ML0925404602009-09-10010 September 2009 Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ ML0920306202009-07-31031 July 2009 Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station ML0917002962009-07-30030 July 2009 Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months ML0835705252008-12-24024 December 2008 Meeting Notice, Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Pre-Application of Post-fire Safe Shutdown Issues at Wolf Creek ML0829405182008-11-10010 November 2008 Renewal of Full-Power Operating License for the Wolf Creek Generating Station, Unit 1 ML0813006882008-05-0909 May 2008 03/05/2008 Meeting Minutes of Subcommittee on Plant License Renewal Regarding Wolf Creek Generating Station ML0812001002008-04-29029 April 2008 End of Cycle Meeting with Wolf Creek Nuclear Operation Corporation IR 05000482/20080072008-04-24024 April 2008 IR 05000482-08-007, on 01/15/2008 - 03/13/2008, Wolf Creek Generating Station, NRC Special Inspection ML0810805452008-04-18018 April 2008 05/01/2008-Notice of Forthcoming Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Safety Evaluation Report Open Items Related to Metal Fatigue Analyses for License Renewal ML0807904692008-04-10010 April 2008 Summary of Teleconference with Wolf Creek Nuclear Operating Corporation, Ameren Union Electric Company for Callaway Plant, and Performance Contracting, Inc. Containment Sump Head Loss Testing ML0802500852008-03-26026 March 2008 Summary of Second Conference Call Held on January 16, 2008, with PWR Licensees on New Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0807404192008-03-14014 March 2008 Assessment of Inspections of Dissimilar Metal Butt Welds in a Retired Pressurizer ML0807304562008-03-13013 March 2008 Cy 2007 Baseline Inspection Completion ML0804503232008-03-0303 March 2008 Summary of Third Conference Call Held with Pressurized-Water Reactor Licensees on Status of NRC Review of License Amendment Requests for Steam Generator Tube Inspections ML0807300242008-02-22022 February 2008 Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1 ML0804504682008-02-19019 February 2008 Federal Register Notice Regarding the Meeting of the ACRS Subcommittee on Wolf Creek Plant License Renewal Application, March 5, 2008 ML0803603712008-02-0707 February 2008 Advisory Sub-Committee on Reactor Safeguards Review of the Wolf Creek Generating Station, License Renewal Application - Safety Evaluation Report with Open Items ML0800901542008-01-22022 January 2008 Summary of Conference Call Held with PWR Licensees on the Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages ML0733103642007-11-27027 November 2007 Revised Notice of Meeting with Wolf Creek Nuclear Operating Corp, to Discuss NRC Staff'S Request for Information on Licensee'S Supplemental Letter Dated September 27, 2007, to the Application Dated February 21, 2006, to Revise TS 5.5.9 ML0733101982007-11-27027 November 2007 Notice of Meeting with Wolf Creek Nuclear Operating Corporation, to Discuss NRC Staff'S Request for Additional Information on Licensee'S Proposed Main Steam and Feedwater Isolation System Modification in Its Application Dated March 14, 2007 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) 2024-09-24
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November 21, 2007 MEMORANDUM TO: Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Jack N. Donohew, Senior Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
WOLF CREEK GENERATING STATION - KEY ISSUES FOR DISCUSSION FOR NOVEMBER 28, 2007, MEETING ON STEAM GENERATOR TUBE INSPECTION LICENSE AMENDMENT (TAC NO. MD0197)
Enclosed are six key issues to be addressed by Wolf Creek Nuclear Operating Corporation at the scheduled meeting next week on November 28, 2007. These issues were sent to the licensee by email on November 20, 2007, so that the licensee would be able to discuss the issues in the meeting.
These issues are based on the staffs review of the licensees application dated February 21, 2006, as supplemented by letters dated May 3 and September 27, 2007 (Agencywide Documents Access and Management System Accession Nos. ML060600456, ML071290104, and ML072750610, respectively).
Docket No. 50-482 Enclosure
ML073250003 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME JDonohew JBurkhardt Thiltz, JND for DATE 11/21/07 11/21/07 11/21/07 MEETING AGENDA - KEY ISSUES FOR DISCUSSION MEETING OF NOVEMBER 28, 2007, FOR TAC NO. MD0197 WOLF CREEK GENERATING STATION
- 1. The staff wishes to discuss the conservatism of the crevice pressures used in the H*analyses. The use of the limiting median crevice pressure approach (see Appendix C of latest RAI response) seems to the staff to only be conservative for the upper region of the H* region and to be potentially non-conservative in the lower region of the H*
which is where most of the axial force on the tube must be reacted. The staff would like to understand why the use of an elevation-dependant crevice pressure based directly on the White Paper test results (i.e., Appendix C) is not needed to ensure a conservative analysis.
- 2. The staff wishes to discuss the conservatism of the assumed residual pullout resistance of [proprietary value] associated with the hydraulic expansion process with respect to the minimum residual pullout strength which may be exhibited among the 21,500 tubes in the Wolf Creek steam generators.
- 3. Depending on the result of the discussions on issues 1 and 2 above, the staff may like to discuss whether or not these issues can be mitigated by taking actions (e.g., divider plate weld inspections) to ensure that the divider plate will remain intact.
- 4. The staff wishes to discuss its continuing concern about the potential for progressive, incremental slippage of the tubes within the tubesheet under normal operating conditions (see most recent RAI questions 8 and 9) and the need to monitor the tubing to ensure that such slippage is not taking place.
- 5. The tubesheet zones shown in Figure 11-4 in Attachment C do not appear to be consistent with those in the table entitled, Steam Generator Tube Inspection Depths for the cold leg in the proposed technical specification amendment. The licensee is requested to explain this apparent inconsistency and whether any corrections are needed.
- 6. It would be helpful to the staff if tables and figures comparable to those in Appendix C could be provided at the meeting for the case of a fully intact divider plate to tubesheet weld (i.e., divider plate factor equal to 0.399).