Letter Sequence Withdrawal |
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TAC:MD0197, Steam Generator Tube Integrity (Withdrawn, Closed) |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
Exelon Generation 4300 Winfield Road Warrenville, IL 60555 RS-08-047 April 1,2008 www.exeloncorp.com Nuclear 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Withdrawal of License Amendment Request Related Steam Generator Tube Alternate Repair Criteria
References:
(1) Letter from K. R. Jury (Exelon Generation Corporation, LLC) to the U. S. Nuclear Regulatory Commission, "Application for Steam Generator Tube Alternate Repair Criteria Technical Specification Amendment," dated November 29,2007 (2) Letter from T. J. Garrett (Wolf Creek Nuclear Operating Corporation) to the U. S. Nuclear Regulatory Commission, "Docket No. 50-482: Withdrawal of License Amendment Request for a Permanent Alternate Repair Criteria in Technical Specification (TS) 5.5.9, 'Steam Generator (SG) Program,'" dated February 14, 2008 (3) Letter from B. K. Singal (U. S. Nuclear Regulatory Commission) to R. A.
Muench (Wolf Creek Nuclear Operating Corporation), "Wolf Crek Generating Station - Withdrawal of License Amendment Request on Steam Generator Tube Inspections (TAC No. MD0197)," dated February 28,2008 The purpose of this letter is to withdraw the Reference 1 submittal from NRC review. In this submittal, Exelon Generation Company, LLC (EGC) requested an amendment to Appendix A Technical Specifications (TS), of Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and NPF-66 for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, respectively to revise the TS requirements related to steam generator tube integrity.
April 1, 2008 U. S. Nuclear Regulatory Commission Page 2 Specifically, the request proposed an Alternate Repair Criteria (ARC) that would revise Technical Specification (TS) 5.5.9, "Steam Generator (SG) Program," to permanently exclude, from eddy current inspection, the portion of the tube below 17 inches from the top of the tubesheet in the Braidwood Station, Unit 2, and Byron Station, Unit 2, steam generators.
The Reference 2 Wolf Creek Nuclear Operating Corporation (WCNOC) withdrawal letter summarized the issues preventing the NRC's approval of the permanent ARC in time for Spring 2008 outages. Reference 3 acknowledged the WCNOC license amendment withdrawal request and provided, as Enclosure 2, a discussion of the remaining technical issues related to the WCNOC permanent ARC submittal.
Mr. T. McGinty (NRC) during a discussion with Mr. D. Benyak (EGC) expressed that the technical issues documented in Reference 3 also impact Reference 1. EGC has reviewed the list of technical issues and concurs that many are common to the EGC Reference 1 submittal. Therefore, EGC withdraws the Braidwood Station and Byron Station ARC proposal until these issues are resolved.
EGC will continue to work with the industry, Westinghouse Electric Company LLC, and the NRC on this issue and supports the use of the expert panel to aid in the resolution of the open technical issues regarding the approval of the permanent ARC (i.e., the H*/B*
methodology).
This letter contains no regulatory commitments. If you have any questions about this letter, please contact David Chrzanowski at (630) 657-2816.
Respectfully,
- Patrick R. Si son Manager - Licensing
