ML18207A264
| ML18207A264 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, Crane  (DPR-018, DPR-019, DPR-025, DPR-029, DPR-030, DPR-044, DPR-050, DPR-053, DPR-056, DPR-059, DPR-063, DPR-069, NPF-011, NPF-018, NPF-037, NPF-039, NPF-062, NPF-066, NPF-069, NPF-072, NPF-077, NPF-085) |
| Issue date: | 07/30/2018 |
| From: | Blake Purnell Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Generation Co |
| Purnell B | |
| References | |
| EPID L-2018-LLR-0076 | |
| Download: ML18207A264 (3) | |
Text
Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C 20555-0001 July 30, 2018 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; R. E. GINNA NUCLEAR POWER PLANT; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -WITHDRAWAL OF REQUEST TO USE ASME CODE CASE N-879 (EPID L-2018-LLR-0076)
Dear Mr. Hanson:
By application dated May 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18151A023), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request for a proposed alternative to the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a, "Codes and standards," and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for Braidwood Station, Units 1 and 2; Byron Station, Unit Nos. 1 and 2; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; Quad Cities Nuclear Power Station, Units 1 and 2; R. E. Ginna Nuclear Power Plant; and Three Mile Island Nuclear Station, Unit 1. The proposed alternative would allow the licensee to use ASME Code Case N-879, "Use of Micro-Alloyed Carbon Steel Bar in Patented Mechanical Joints and Fittings, Classes 1, 2, and 3, Section Ill, Division 1."
By letter dated July 10, 2018 (ADAMS Accession No. ML18186A545), the U.S. Nuclear Regulatory Commission (NRC) staff informed Exelon that supplemental information was needed for the staff to begin its detailed technical review of the application. By letter dated July 26, 2018 (ADAMS Accession No. ML18208A345), Exelon requested to withdraw the application for the proposed alternative to use ASME Code Case N-879. The staff acknowledges Exelon's request to withdraw the application. The staff's review of the application has ceased and EPID L-2018-LLR-0076 has been closed.
If Exelon decides to resubmit the request for the proposed alternative, the application must provide a plant-specific justification for the proposed alternative that includes the information the NRC requested in its July 10, 2018, letter. Future applications should be limited to a single facility. Prior to resubmitting, Exelon should participate in a pre-application meeting with the NRC staff to discuss its planned application.
Exelon requested the proposed alternative for the lifetime of its facilities. The NRC staff does not generally approve alternatives to 10 CFR 50.55a and the ASME codes beyond the current inservice inspection or testing intervals, unless specific circumstances would justify a longer interval. For example, the NRC staff has approved alternatives for the next inservice inspection or testing interval when it is near the end of the current interval and the ASME code requirements for the next interval are already incorporated in the rule.
If you have any questions, please contact me at (301) 415-1380.
Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-317, 50-318, 50-461, 50-237, 50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-277, 50-278, 50-254, 50-265, 50-244, and 50-289 cc: Distribution via Listserv Sincerely,
/Jl I~
Blake Purnell, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML18207A264 OFFICE DORL/LPL3/PM NAME BPurnell DATE 7/30/18 OFFICE DE/EMIB/BC NAME SBailey*
DATE 7/30/18 RidsNrrPMByron Resource RidsNrrPMCalvertCliffs Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMFitzPatrick Resource RidsNrrPMLaSalle Resource RidsNrrPMLimerick Resource RidsNrrPMNineMilePoint Resource RidsNrrPMPeachBottom Resource RidsN rrPMQuadCities Resource RidsNrrPMREGinna Resource RidsNrrPMThreeMilelsland Resource GCheruvenki, NRR RDavis, NRR CBasavaraju, NRR
- by email DORULPL3/LA DMLR/MPHB/BC SRohrer SRuffin*
7/30/18 7/30/18 DORULPL3/BC DORULPL3/PM DWrona BPurnell 7/30/18 7/30/18