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TAC:MD0197, Steam Generator Tube Integrity (Withdrawn, Closed) |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 06-0014, Notice of Intent to Upgrade to Digital Main Steam and Feedwater Isolation Valve Controls2006-03-28028 March 2006
Notice of Intent to Upgrade to Digital Main Steam and Feedwater Isolation Valve Controls
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 NRCs 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 07-0042, Followup Response to NRC Requests for Additional Information Related to License Renewal Application2007-09-27027 September 2007
Followup Response to NRC Requests for Additional Information Related to License Renewal Application
Project stage: Response to RAI
ML0732700972007-09-27027 September 2007
ARB Disposition Record, Callaway, Discuss Concerned Individuals Rebuttal Letter for Allegation Files RIV-2007-A-0028 and RIV-2007-A-0048
Project stage: Request
ML0727506102007-09-27027 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 Staffs Request for Additional Information on Licensees 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
ET 08-0006, Response to NRC Review of License Amendment Request to Revise the Steam Generator Program2008-01-25025 January 2008
Response to NRC Review of License Amendment Request to Revise the Steam Generator Program
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
2007-07-11
[Table View] |
Text
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).
