NRC 2004-0079, Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 236

Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 236

ML042300369
Person / Time
Site:	Point Beach
Issue date:	08/03/2004
From:	Koehl D Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2004-0079, TAC MC0873, TAC MC0874
Download: ML042300369 (2)

Text

- Committed to NuclearExcellen Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC August 3, 2004 NRC 2004-0079 10 CFR 50.67 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Request for Withdrawal of Request for Exemptions to 10 CFR 50.61. Appendices G and H to 10 CFR 50. Approval of PTS Application for PBNP Unit 2 and Withdrawal of Associated License Amendment Request 236 (TAC Nos. MC0873 and MC0874)

Reference:

1) Letter from NMC to NRC dated September 26, 2003 (NRC 2003-0091)

2) Letter from NMC to NRC dated January 26, 2004 (NRC 2004-0011)

3) NRC Memorandum from Luis A. Reyes to Chairman Diaz, et a/, dated May 27, 2004, "Pressurized Thermal Shock Analyses for Renewal of Certain Nuclear Power Plant Operating Licenses" In reference 1, Nuclear Management Company, LLC (NMC), submitted a request for NRC review and approval of certain exemptions, which would have allowed use of the Master Curve methodology for determining the adjusted RTNDT (reference nil-ductility temperature) of the Point Beach Nuclear Plant (PBNP) Unit 2 reactor vessel limiting circumferential weld metal. This method is used for Pressurized Thermal Shock (PTS) screening evaluation and was submitted in support of PBNP license renewal.

In association with the request for exemptions to support the Master Curve methodology, a revised reference in PBNP Technical Specification (TS) 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)", was also submitted. The proposed amendment would have modified TS 5.6.5, to add a reference to the issuance date of the NRC safety evaluation accepting the new Master Curve Methodology for Unit 2. Reference 2 supplemented this amendment request.

Reference 3 discusses license renewal options for demonstrating that time-limited aging analyses (TLAAs) requiring evaluation have been assessed and that activities authorized by a renewed license will continue to be conducted in accordance with the plant's current licensing basis. 10 CFR 54.21(c)(1)(iii) allows a licensee to demonstrate that the effects of aging will be adequately managed for the period of extended operation and permits a license renewal applicant to elect not to extend the existing TLAA.

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• . Document Control Desk Page 2 Based on a telephone conference held with NRC staff on July 21, 2004, regarding the information discussed in reference 3, as well as delays in approval of the Master Curve methodology, NMC hereby requests that the submittals identified in references I and 2 be withdrawn.

NMC intends to provide a submittal demonstrating that the affects of aging of the reactor vessel will be managed as part of the PTS TLAA as discussed in reference 3.

This demonstration is needed to support the PBNP license renewal application that was submitted to NRC on February 25, 2004.

This letter contains no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and accurate. Executed on August 3, 2004.

Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC cc: Regional Administrator, Region ll, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW