RS-17-087, Withdrawal of Inservice Inspection Relief Request I4R-03 Re Examination of the Reactor Pressure Vessel (RPV) Stabilizer Bracket Welds Due to Impracticality
| ML17200C937 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/17/2017 |
| From: | Gullott D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-17-087 | |
| Download: ML17200C937 (2) | |
Text
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630 657 ?000 Olfice 10 CFR 50.55a RS-17-087 July 17, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Withdrawal of lnservice Inspection Relief Request 14R-03 Regarding Examination of the Reactor Pressure Vessel (RPV) Stabilizer Bracket Welds Due to Impracticality
References:
- 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "LaSalle County Station, Units 1 and 2, Fourth 10-Year Interval lnservice Inspection Program Relief Requests," dated May 30, 2017
- 2) Letter from R. Gibbs (U.S. Nuclear Regulatory Commission) to C. G. Pardee (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2 -
Third 10-Year Interval lnservice Inspection Program Plan Request for Relief Nos. 13R-03, l3R-04, 13R-08, 13R-09, and 13R-10 for (TAC Nos. MD5459, MD5460, MD5390, MD5463, MD5464, MD 5465, MD5466, MD5467, and MD5468)," dated January 30, 2008
- 3) Federal Register, Volume 76, No. 119, dated June 21, 2011 (76 FR 36232)
In a letter dated May 30, 2017 (Reference 1 ), Exelon Generation Company, LLC (EGC) requested approval of a request associated with the Fourth 10-Year Interval lnservice Inspection (ISi) Program for the LaSalle County Station (LSCS), Units 1 and 2. The Fourth interval of the LSCS ISi Program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2007 Edition with the 2008 Addenda.
The purpose of this letter is to formally withdraw one of the eight relief requests that were transmitted with Reference 1. Specifically, EGG is withdrawing the following relief request:
1 Relief Request 14R-03 regarding examination of the reactor pressure vessel (RPV)
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stabilizer bracket welds - Relief Requested In Accordance with 1 O CFR 50.55a(g)(5)(iii)r\\ \\V -0
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July 17, 2017 U.S. Nuclear Regulatory Commission Page2 LSCS Relief Request 14R-03 was submitted citing Reference 2 as a precedent. In Reference 2, the NRC authorized the request in accordance with 10 CFR 50.55a(g)(5)(iii). Access to petiorm sutiace examinations of these integral attachment welds was not possible due to the limited space available between the permanent RPV insulation and radiological bio-shield wall.
As discussed with the NRC on June 28, 2017, and as stated in the Code of Federal Regulations and in Reference 3, the NRC has revised 1 O CFR 50.55a(g)(5)(iii) to clarify that determinations of impracticality must be based on the demonstrated limitations experienced when attempting to comply with the Code requirements during the inservice inspection interval for which the request is being submitted. A request for relief must be submitted after the necessary examination has been attempted during a given ISi interval and the ASME B&PV Code requirement determined to be impractical. Because of this clarification and since the Fourth 10-Year Interval examinations have not yet been petiormed, LSCS relief request 14R-03 is being withdrawn.
There are no regulatory commitments contained within this letter.
Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630) 657-2815.
Respectfully, David M. Gullett Manager - Licensing Exelon Generation Company, LLC cc:
Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station J