RS-17-163, Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval

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Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval
ML17331A623
Person / Time
Site: Byron  Constellation icon.png
Issue date: 11/20/2017
From: Gullott D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-17-163
Download: ML17331A623 (2)


Text

4300 WinfiGld Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Officr>

RS-17-163 10 CFR 50.55a(z)

November 20, 2017 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D.C. 20555-0001 Byron Station, Units 1 and 2 Renewed FaciUty Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

Withdrawal of Relief Request RV-2 Associated with the Fourth lnservice Testing Interval

References:

1) Letter from D. M. Gullett (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request RV-2 Associated with the Fourth lnservice Testing Interval," dated September 25, 2017
2) Letter from J. Wiebe (U.S. Nuclear Regulatory Commission) to B. C. Hanson (Exelon Generation Company, LLC), "Byron Station, Unit Nos. 1 and 2, Nonacceptance of Relief Request RV-2 Related to Extension of Pressure Relief Valve Testing Intervals," dated November 1, 2017 In Reference 1, Exelon Generation Company, LLC (EGC) requested approval of a proposed alternative to the requirements of American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition through the 2006 Addenda. The relief request was associated with the Fourth lnservice Testing Interval for Byron Station, Units 1 and 2, which is in effect from July 1, 2016 through June 30, 2026.

The purpose of this letter is to formally withdraw the relief request that was transmitted with Reference 1 . Specifically, EGG is withdrawing the following relief request: Relief Request RV-2, Test Interval for Classes 2 and 3 Pressure Relief Valves per Mandatory Appendix I, 1-1350 Proposed Alternative Requested in Accordance with 10 CFR 50.55a(z)(1).

The relief request proposed to extend the test frequency for a limited number of pressure relief valves (PRVs) from 48 months to 54 months to allow implementation of a "divisional outage strategy" during refueling outages. The basis of the request was that the proposed alternative would provide an acceptable level of quality and safety while effectively monitoring the associated components for degradation.

This withdrawal request and the NRC staff determination were discussed by teleconference with the NRC on November 1, 2017, as stated in Reference 2. Withdrawal is requested due to the NRG staff determination that extending the test frequency from 48 months to 54 months is not

November 20, 2017 U.S. Nuclear Regulatory Commission Page 2 for operational convenience and can be performed in accordance with ASME Code Case OMN-20 lnservice Test Frequency." EGG plans to apply the OMN-20 extension to allow PAV testing to be performed within a 54 month interval, i.e., applying OMN-20 to extend the test intervals by up to 6 months, allowing implementation of the "divisional outage strategy" for Byron Station, Units 1 and 2, refueling outages.

There are no regulatory commitments contained within this letter.

Should you have any questions concerning this letter, please contact Ryan M. Sprengel at (630) 657-2814.

Respectfully, David M. Gullott Manager- Licensing Exelon Generation Company, LLC cc: NRG Regional Administrator- Region Ill NRG Senior Resident Inspector- Byron Station NRC Project Manager, NRA - Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety